The 13th International Conference on Environmental ... - Events
The 13th International Conference on Environmental ... - Events
The 13th International Conference on Environmental ... - Events
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FINAL PROGRAM<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> <str<strong>on</strong>g>13th</str<strong>on</strong>g> <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> <strong>on</strong><br />
Envir<strong>on</strong>mental Remediati<strong>on</strong> and<br />
Radioactive Waste Management<br />
October 3-7, 2010 – Tsukuba, Japan, Epochal Tsukuba<br />
http://www.jsme.or.jp/pes/ICEM10/<br />
http://www.asmec<strong>on</strong>ferences.org/ICEM2010/
ASME Message<br />
ICEM2010 is the thirteenth in a series of internati<strong>on</strong>al c<strong>on</strong>ferences <strong>on</strong><br />
envir<strong>on</strong>mental remediati<strong>on</strong> and radioactive waste management organized by ASME, in<br />
cooperati<strong>on</strong> with various agencies and other technical societies. While the sp<strong>on</strong>soring leads<br />
are the Envir<strong>on</strong>mental Engineering and the Nuclear Engineering Divisi<strong>on</strong>s within ASME, it<br />
provides a focus <strong>on</strong> envir<strong>on</strong>mental restorati<strong>on</strong> and radioactive waste management for the<br />
entire ASME. Founded in 1880 as the American Society of Mechanical Engineers, today's<br />
ASME promotes the art, science & practice of mechanical & multidisciplinary engineering<br />
and allied sciences around the globe –with >120,000 members worldwide.<br />
Having chaired various ICEM c<strong>on</strong>ferences, I learned firsthand that success<br />
results <strong>on</strong>ly through the c<strong>on</strong>certed effort of many individuals and organizati<strong>on</strong>s. If I tried<br />
to menti<strong>on</strong> all, I would certainly fail, however, I must acknowledge the dedicati<strong>on</strong> of the<br />
<str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Secretary, Hiroyoshi Ueda, the c<strong>on</strong>tinued support of the US Department of<br />
Energy, the Technical and Track Chairs, numerous volunteers and organizati<strong>on</strong>al sp<strong>on</strong>sors,<br />
and most of all, the presenters and program participants. Thank you for being here.<br />
I first served as <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Chair during ICEM ’01, which was held in Bruges,<br />
Belgium, during uncertain times for the world – just a few days after a terrorist attack of<br />
the United States. Since then the world has changed and the global envir<strong>on</strong>ment has<br />
become much more pers<strong>on</strong>al. My pers<strong>on</strong>al message for ICEM’01 was of to collect the best<br />
of ideas, and “inclusi<strong>on</strong>”. While not intenti<strong>on</strong>al, it became the first of a series of thematic,<br />
clear, and simple messages.<br />
ICEM returned to Bruges in 2007, and my message had two parts. I believe<br />
that they are even more valid today. First, that Educati<strong>on</strong>, Energy, Envir<strong>on</strong>ment, and the<br />
Ec<strong>on</strong>omy are inextricably intertwined, and therefore the logical development of <strong>on</strong>e is<br />
str<strong>on</strong>gly dependent <strong>on</strong> the health of the others. And sec<strong>on</strong>d, that Society demands to be<br />
actively informed --that is, to be aware of the details that influence their reas<strong>on</strong>able<br />
expectati<strong>on</strong> of an adequate return <strong>on</strong> their investment in Governance. In today's world,<br />
Global Envir<strong>on</strong>mental Partnerships and cooperative agreements are essential in order to<br />
dem<strong>on</strong>strate good Governance.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> message for ICEM2010 is “A clean envir<strong>on</strong>ment sustained by nuclear<br />
energy”. It is as simple as that.<br />
Please note that ICEM2011 will be held in Reims (France) <strong>on</strong> September 2011.<br />
A call for papers appears at: icemc<strong>on</strong>f.com/2011CallforPapers/tabid/494/Default.aspx. I<br />
look forward to an intensive exchange of ideas, and to the explorati<strong>on</strong> of new partnerships.<br />
After all that, the <strong>on</strong>ly thing left is to Welcome You to the ICEM2010 <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> <strong>on</strong> behalf<br />
of ASME.<br />
Aníbal L. Taboas<br />
ASME Fellow<br />
Technical Co-Chair, ICEM2010<br />
October 2010, Tsukuba, Japan
General Informati<strong>on</strong><br />
Objectives and Background<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> <str<strong>on</strong>g>13th</str<strong>on</strong>g> <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> <strong>on</strong><br />
Envir<strong>on</strong>mental Remediati<strong>on</strong> and Radioactive Waste<br />
Management (ICME2010) is the thirteenth in a<br />
series of internati<strong>on</strong>al c<strong>on</strong>ferences organized by the<br />
ASME and other technical societies, and being held<br />
in Japan after an eleven year interval. ICEM was<br />
first held in H<strong>on</strong>g K<strong>on</strong>g in 1987, followed by Kyoto,<br />
Japan in 1989; Seoul, Korea, in 1991; Prague, Czech<br />
Republic, in 1993; Berlin, Germany, in 1995;<br />
Singapore in 1997; Nagoya, Japan in 1999; Bruges,<br />
Belgium in 2001 and 2007; Oxford, UK in 2003;<br />
Glasgow, Scotland in 2005; and Liverpool, UK in<br />
2009.<br />
ICEM promotes broad global exchange of<br />
informati<strong>on</strong> <strong>on</strong> technologies, operati<strong>on</strong>s,<br />
management approaches, ec<strong>on</strong>omics and public<br />
policies in the critical areas of envir<strong>on</strong>mental<br />
remediati<strong>on</strong> and radioactive waste management.<br />
ICEM also provides a unique opportunity to foster<br />
cooperati<strong>on</strong> am<strong>on</strong>g specialists in mature<br />
envir<strong>on</strong>mental management programs and those<br />
involved in emerging programs. Attendees include<br />
scientists and engineers, suppliers and vendors,<br />
utilities, regulators government, and others seeking<br />
soluti<strong>on</strong> to envir<strong>on</strong>mental problems. Over 30<br />
countries are generally represented in ICEM<br />
c<strong>on</strong>ferences.<br />
<str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Co-Sp<strong>on</strong>sors<br />
ICEM2010 is co-sp<strong>on</strong>sored by:<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Power and Energy System Divisi<strong>on</strong> of the Japan<br />
Society of Mechanical Engineers (JSME),<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Divisi<strong>on</strong> of Nuclear Fuel Cycle and<br />
Envir<strong>on</strong>ment of the Atomic Energy Society of Japan<br />
(AESJ), and<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Envir<strong>on</strong>mental Engineering and the Nuclear<br />
Engineering Divisi<strong>on</strong>s of the American Society of<br />
Mechanical Engineers (ASME).<br />
Supporting Organizati<strong>on</strong>s<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> following nati<strong>on</strong>al/internati<strong>on</strong>al organizati<strong>on</strong>s<br />
support the c<strong>on</strong>ference:<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Japan Atomic Energy Agency<br />
Tokyo Electric Power Company<br />
Nuclear Waste Management Organizati<strong>on</strong> of<br />
Japan<br />
Radioactive Waste Management Funding and<br />
Research Center<br />
1<br />
Tsukuba City<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy Agency<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Canadian Nuclear Society<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Chinese Nuclear Society<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Korean Nuclear Society<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Korean Radioactive Waste Society<br />
<str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Formant<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> ICEM2010 technical program includes<br />
c<strong>on</strong>current sessi<strong>on</strong>s in six technical tracks:<br />
� Low/Intermediate-Level Radioactive Waste<br />
(L/ILW)<br />
� Spent Fuel, Fissile Material, Transuranic and<br />
High-Level Radioactive Waste (SF/TRU/HLW)<br />
� Facility Dec<strong>on</strong>taminati<strong>on</strong> and<br />
Decommissi<strong>on</strong>ing (D&D)<br />
� Envir<strong>on</strong>mental Remediati<strong>on</strong> (ER)<br />
� Envir<strong>on</strong>mental Management, Public<br />
Involvement and Crosscutting Issues (EM/PI)<br />
� Global Partnership and Multi-Nati<strong>on</strong>al<br />
Programs (GP)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> technical program c<strong>on</strong>sists of an opening<br />
plenary sessi<strong>on</strong> and several parallel program tracks<br />
with up to six c<strong>on</strong>current sessi<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> sessi<strong>on</strong>s<br />
include 25 minute oral presentati<strong>on</strong>s, panels, and<br />
poster displays which are designed to enhance<br />
dialogue between presenters and participants. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
program is divided into 36 sessi<strong>on</strong>s c<strong>on</strong>ducted over<br />
three days. A listing of the specific sessi<strong>on</strong>s within<br />
each of the six technical program tracks can be<br />
found in the secti<strong>on</strong> for the technical sessi<strong>on</strong>s.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> full registrati<strong>on</strong> fee includes meeting materials<br />
in the c<strong>on</strong>ference bag, entrance to all sessi<strong>on</strong>s and<br />
the exhibiti<strong>on</strong>, the welcome recepti<strong>on</strong> in the Sunday<br />
evening, lunch in the exhibiti<strong>on</strong> area and the banquet<br />
in the Tuesday evening. Each registrant will receive<br />
the c<strong>on</strong>ference proceedings <strong>on</strong> a CD-ROM mailed<br />
after the c<strong>on</strong>ference.<br />
<str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Venue<br />
ICEM2010 is being held at the Tsukuba<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> C<strong>on</strong>gress Center, Epochal Tsukuba,<br />
which is home to many internati<strong>on</strong>ally renowned<br />
scientists.<br />
City of Tsukuba<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> City of Tsukuba is about 50 km northeast of<br />
Tokyo and 40 km northwest of Narita Airport. It<br />
covers an area of 28,000 ha with a populati<strong>on</strong> of<br />
about 200,000. To the north lies Mount Tsukuba,
877 meters above sea level. Seen from <strong>on</strong>e angle,<br />
Tsukuba city, with its streets of traditi<strong>on</strong>al stores and<br />
houses, has the look of a rural refuge of abundant<br />
greenery. Seen from another angle, it is Tsukuba<br />
Science City, a superb modern urban landscape<br />
seldom seen in Japanese cities.<br />
<str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Check-In<br />
Up<strong>on</strong> your arrival, please check-in, or <strong>on</strong>-site<br />
register, at the Registrati<strong>on</strong> Desk and receive your<br />
own badge, i.e. registrati<strong>on</strong> pass, and other materials.<br />
It is str<strong>on</strong>gly recommended that the c<strong>on</strong>ference<br />
participants check-in <strong>on</strong> Sunday, October 3, to avoid<br />
the rush before the opening sessi<strong>on</strong> <strong>on</strong> M<strong>on</strong>day<br />
morning, October 4. Badges are required for the<br />
Welcome Recepti<strong>on</strong> in the Sunday evening. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
Registrati<strong>on</strong> Desk is located in the entrance hall <strong>on</strong><br />
the ground floor, during the following hours:<br />
Sunday, October 3 16:00 to 19:00<br />
M<strong>on</strong>day, October 4 7:30 to 17:00<br />
Tuesday, October 5 7:30 to 17:00<br />
Wednesday, October 6 7:30 to 13:00.<br />
Welcome Recepti<strong>on</strong><br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Welcome Recepti<strong>on</strong> will be held from 18:00,<br />
Sunday, October 3, at the c<strong>on</strong>ference room 101+102<br />
of Epochal Tsukuba, the c<strong>on</strong>ference venue.<br />
Daily Morning Briefing for Speaker/Sessi<strong>on</strong><br />
Co-Chair<br />
All speakers including panelists and sessi<strong>on</strong><br />
co-chairs are invited to the Moring Briefing for<br />
Speaker/Sessi<strong>on</strong> Co-Chair, <strong>on</strong> the day of their oral<br />
presentati<strong>on</strong>/panel discussi<strong>on</strong>/chairing. Coffee and<br />
bread will be served at the briefing. This briefing<br />
will give them the time for final arrangements<br />
before the oral sessi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> attendance at the<br />
briefing will provide an opportunity for the Sessi<strong>on</strong><br />
Co-Chairs to meet with the speakers, and for all to<br />
discuss the topics they will be addressing. It is<br />
essential that all speakers and sessi<strong>on</strong> co-chairs<br />
attend the briefing. <str<strong>on</strong>g>The</str<strong>on</strong>g> briefing will be held at<br />
Rooms 401 through 404 during the following time<br />
slots:<br />
M<strong>on</strong>day, October 4 8:30 to 9:00<br />
Tuesday, October 5 8:00 to 8:30<br />
Wednesday, October 6 8:00 to 8:30.<br />
Lunch and Coffee in Exhibiti<strong>on</strong> Area<br />
Lunch will be served in the exhibiti<strong>on</strong> area,<br />
Multi-Purpose Hall <strong>on</strong> the ground floor. Lunches<br />
served <strong>on</strong> M<strong>on</strong>day, Tuesday and Wednesday will<br />
2<br />
mainly c<strong>on</strong>sist of a light meal that can be easily<br />
c<strong>on</strong>sumed while visiting the exhibits. <str<strong>on</strong>g>The</str<strong>on</strong>g> full<br />
registrati<strong>on</strong> fee includes the lunche<strong>on</strong> price for all<br />
three days. If you prefer, there are also several local<br />
restaurants near the c<strong>on</strong>ference venue. During the<br />
breaks, coffee/tea will be served in the exhibiti<strong>on</strong><br />
area.<br />
Banquet<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Banquet will be held from 18:30, Tuesday,<br />
October 5, at Banquet Hall "Subaru" <strong>on</strong> the ground<br />
floor of the annex building of Okura Fr<strong>on</strong>tier Hotel<br />
Tsukuba.<br />
Preparatory PC for Speakers<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> preparatory PC will be available in Room 301<br />
for speakers to load and review their PowerPoint<br />
slides. PC in each oral sessi<strong>on</strong> room will be also<br />
available at the breaks for speakers to check their<br />
slides.<br />
Paid Business Services and Internet<br />
Paid Business Services are provided <strong>on</strong> the ground<br />
floor (See “Floor Map of Epochal Tsukuba and Paid<br />
Business Services” page.) Wireless Internet is<br />
available in the public area.<br />
Technical Tour<br />
All foreign participants are required to carry their<br />
passports to the tour for the security checks. A full<br />
day tour to Tokai-Mura, <strong>on</strong>e of the well-known<br />
nuclear sites in Japan, will be held <strong>on</strong> October 7.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> tour will integrate visits to ENTRY, JAEA’s<br />
research facility for the geological disposal, and the<br />
decommissi<strong>on</strong>ing site of a JAPC’s gas-cooled<br />
reactor, Tokai-1. (<str<strong>on</strong>g>The</str<strong>on</strong>g> tour is full.)<br />
Exhibiti<strong>on</strong><br />
An industrial exhibiti<strong>on</strong> will be held in c<strong>on</strong>juncti<strong>on</strong><br />
with the c<strong>on</strong>ference sessi<strong>on</strong>s during the following<br />
hours:<br />
M<strong>on</strong>day, October 4 9:00 to 18:00<br />
Tuesday, October 5 9:00 to 18:00<br />
Wednesday, October 6 9:00 to 13:30<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Exhibiti<strong>on</strong> Area will be Multi-Purpose Hall <strong>on</strong><br />
the ground floor.
Insurance and Liability<br />
All participants are encouraged to make their own<br />
arrangements for health and travel insurance.<br />
Neither JSME, AESJ, ASME nor their agents can be<br />
held resp<strong>on</strong>sible for any pers<strong>on</strong>al injury, loss,<br />
damage, accident to private property or additi<strong>on</strong>al<br />
expenses incurred because of delays or changes in<br />
air, rail, sea, road or other services, strikes, sickness,<br />
weather or any other cause.<br />
Disclaimer<br />
Neither JSME, AESJ nor ASME can accept any<br />
liability for death, injury, or any loss, cost or<br />
expense suffered or incurred by any pers<strong>on</strong> if such<br />
loss is caused or results from the act, default or<br />
omissi<strong>on</strong> of any pers<strong>on</strong> other than an employee or<br />
agent of JSME, AESJ or ASME. In particular,<br />
neither JSME, AESJ nor ASME can accept any<br />
liability for losses arising from the provisi<strong>on</strong> or<br />
n<strong>on</strong>-provisi<strong>on</strong> of services provided by hotel<br />
companies or transport operators. Nor can JSME,<br />
AESJ nor ASME accept liability for losses suffered<br />
by reas<strong>on</strong> of war including threat of war, riot and<br />
civil strife, terrorist activity, natural disaster, weather,<br />
flood, drought, technical, mechanical or electrical<br />
breakdown within any premises visited by delegates<br />
and/or partners in c<strong>on</strong>necti<strong>on</strong> with the c<strong>on</strong>ference,<br />
industrial disputes, governmental acti<strong>on</strong>, regulati<strong>on</strong>s<br />
or technical problems which may affect the services<br />
provided in c<strong>on</strong>necti<strong>on</strong> with the c<strong>on</strong>ference. Neither<br />
JSME, AESJ nor ASME is able to give any warranty<br />
that a particular pers<strong>on</strong> will appear as a speaker or<br />
panelist.<br />
3<br />
Technical Sessi<strong>on</strong> Schedule<br />
Opening Sessi<strong>on</strong><br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> opening sessi<strong>on</strong> will start at 9:30 AM, M<strong>on</strong>day.<br />
Opening/welcome addresses from the c<strong>on</strong>ference<br />
organizers and plenary speeches from<br />
nati<strong>on</strong>al/internati<strong>on</strong>al representatives will be held.<br />
Each speech will be allocated 35 minutes including<br />
questi<strong>on</strong>s and answers.<br />
C<strong>on</strong>current Oral Sessi<strong>on</strong>s<br />
C<strong>on</strong>current sessi<strong>on</strong>s will be held in the six technical<br />
tracks. <str<strong>on</strong>g>The</str<strong>on</strong>g> sessi<strong>on</strong>s will start at 13:30 PM for<br />
M<strong>on</strong>day and at 9:00 AM for Tuesday and<br />
Wednesday. Each presentati<strong>on</strong> will be allocated 25<br />
minutes (20 min. presentati<strong>on</strong> and 5 min. discussi<strong>on</strong>).<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> sessi<strong>on</strong> co-chairs can extend the discussi<strong>on</strong> time,<br />
keeping the time slot of the sessi<strong>on</strong>.<br />
Poster Sessi<strong>on</strong>s<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> poster sessi<strong>on</strong>s will be held at Room 102 during<br />
the following time slots:<br />
M<strong>on</strong>day, October 4 15:15 to 15:40<br />
17:25 to 17:50<br />
Tuesday, October 5 10:20 to 10:45<br />
15:15 to 15:40<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> posters should be set up in M<strong>on</strong>day AM and<br />
torn down by 12:00, Wednesday.
List of Organizati<strong>on</strong> Acr<strong>on</strong>yms<br />
AECL Atomic Energy of Canada Limited<br />
AESJ Atomic Energy Society of Japan<br />
AIST Nati<strong>on</strong>al Institute for Advanced Industrial Science and Technology<br />
ANL Arg<strong>on</strong>ne Nati<strong>on</strong>al Laboratory<br />
ANSTO Australian Nuclear Science and Technology Organisati<strong>on</strong><br />
ASME American Society of Mechanical Engineers<br />
CEA Commissariat à l'énergie atomique<br />
CRIEPI Central Research Institute of Electric Power Industry<br />
EDF Electricité de France<br />
EPRI Electric Power Research Institute<br />
IAE Institute of Applied Energy<br />
IAEA <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy Agency<br />
JAEA Japan Atomic Energy Agency<br />
JAEA/NPSTC JAEA/Nuclear N<strong>on</strong>proliferati<strong>on</strong> Science and Technology Center<br />
JAPC Japan Atomic Power Company<br />
JNES Japan Nuclear Energy Safety Organizati<strong>on</strong><br />
JNFL Japan Nuclear Fuel Limited<br />
JSME Japan Society of Mechanical Engineers<br />
KAERI Korea Atomic Energy Research Institute<br />
KAIST Korea Advanced Institute of Science and Technology<br />
KHNP Korea Hydro and Nuclear Power Company<br />
KNF Korea Nuclear Fuel<br />
KRMC Korea Radiactive Waste Management Corporati<strong>on</strong><br />
LANL Los Alamos Nati<strong>on</strong>al Laboratory<br />
LBNL Lawrence Berkeley Nati<strong>on</strong>al Laboratory<br />
MEXT Ministry of Educati<strong>on</strong>, Culture, Sports, Science and Technology<br />
NEL Nuclear Engineering, Ltd.<br />
NUMO Nuclear Waste Management Organizati<strong>on</strong> of Japan<br />
NWMO Nuclear Waste Management Organizati<strong>on</strong><br />
OECD/NEA Organizati<strong>on</strong> for Ec<strong>on</strong>omic Cooperati<strong>on</strong> and Development/Nuclear Energy Agency<br />
PNNL Pacific Northwest Nati<strong>on</strong>al Laboratory<br />
RWMC Radioactive Waste Management Funding and Research Center<br />
SCK•CEN Studiecentrum voor Kernenergie•Centre d'Etude de l'Energie Nucléaire (Belgian<br />
Nuclear Research Centre)<br />
Tokyo Tech Tokyo Institute of Technology<br />
UCB University of California, Berkeley<br />
US DOE U. S. Department of Energy<br />
US NRC U. S. Nuclear Regulatory Commissi<strong>on</strong><br />
VUB Vrije Universiteit Brussel<br />
4
Map around <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Venue, Hotels and Tsukuba Stati<strong>on</strong><br />
Okura Fr<strong>on</strong>tier Hotel<br />
Tsukuba Epochal<br />
Annex<br />
Okura Fr<strong>on</strong>tier Hotel Tsukuba<br />
(Epochal Tsukuba)<br />
5<br />
Main
Floor Map of Epochal Tsukuba and Paid Business Services<br />
6<br />
Copy, Printer, FAX<br />
Locker<br />
Mailing<br />
Beverage Vending Machine<br />
Informati<strong>on</strong>
ICEM2010 Technical Sessi<strong>on</strong>s at a Glance<br />
9:30<br />
9:45<br />
9:45 - 12:05<br />
12:10 - 13:30<br />
13:30<br />
13:35<br />
14:00<br />
14:25<br />
14:50<br />
15:15 - 15:40<br />
15:45<br />
16:10<br />
16:35<br />
17:00<br />
M<strong>on</strong>day, October 4<br />
Room 405 Room 101 Room 406 Room 202A Room 202B Room 303<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
L1: Waste<br />
Management<br />
Break/Poster<br />
Break<br />
Preparati<strong>on</strong><br />
Main C<strong>on</strong>venti<strong>on</strong> Hall<br />
Opening Sessi<strong>on</strong><br />
Opening and Welcome Addresses<br />
Plenary Speeches from Representatives<br />
Break/Poster<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
L1: Waste<br />
Management<br />
H1: Nati<strong>on</strong>al<br />
and<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g><br />
Programs (1)<br />
H3: Panel<br />
"Radwaste<br />
Human<br />
Resource<br />
Development<br />
to Support the<br />
Nuclear<br />
Renaissance"<br />
D1: Nati<strong>on</strong>al and<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g><br />
D&D Programs<br />
D1: Nati<strong>on</strong>al and<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g><br />
D&D Programs<br />
17:25 - 17:50 Poster Poster Poster Poster Poster Poster<br />
7<br />
Lunch<br />
R1:<br />
Envir<strong>on</strong>mental<br />
Impacts<br />
Break/Poster<br />
R1:<br />
Envir<strong>on</strong>mental<br />
Impacts<br />
M1:<br />
Envir<strong>on</strong>mental<br />
Management<br />
Break/Poster Break/Poster<br />
M1:<br />
Envir<strong>on</strong>mental<br />
Management<br />
H2:<br />
Transportati<strong>on</strong>,<br />
Storage and<br />
Waste Treatment<br />
H2:<br />
Transportati<strong>on</strong>,<br />
Storage and<br />
Waste Treatment
ICEM2010 Technical Sessi<strong>on</strong>s at a Glance<br />
9:00<br />
9:05<br />
9:30<br />
9:55<br />
Room 201 Room 101 Room 202 Room 406 Room 405 Room 303<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
10:20 - 10:45 Break/Poster Break/Poster Break/Poster Break/Poster Break/Poster Break/Poster<br />
10:50<br />
11:15<br />
11:40<br />
12:05<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
12:30 - 13:30 Lunch Lunch Lunch Lunch Lunch Lunch<br />
13:35<br />
14:00<br />
14:25<br />
14:50<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
15:15 - 15:40 Break/Poster Break/Poster Break/Poster Break/Poster Break/Poster Break/Poster<br />
15:45<br />
16:10<br />
16:35<br />
17:00<br />
17:25<br />
Tuesday, October 5<br />
L2: Solidificati<strong>on</strong><br />
and Package<br />
(1)<br />
L2: Solidificati<strong>on</strong><br />
and Package (1)<br />
L4: Solidificati<strong>on</strong><br />
and Package (2)<br />
H4: Nati<strong>on</strong>al and<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g><br />
Programs (2)<br />
H4: Nati<strong>on</strong>al and<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g><br />
Programs (2)<br />
H5: Panel<br />
"Advances in<br />
Knowledge<br />
Management<br />
for Radioactive<br />
Waste<br />
Disposal"<br />
G2: IAEA<br />
Topical for<br />
Disused<br />
Sealed<br />
Radioactive<br />
Sources<br />
(DSRS)<br />
L3: Nuclide<br />
Assay<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
L5: Recycling<br />
and Clearance<br />
H5: Panel<br />
"Advances in<br />
Knowledge<br />
Management<br />
for Radioactive<br />
Waste<br />
Disposal"<br />
D2: Dismantling<br />
and<br />
Dec<strong>on</strong>taminati<strong>on</strong><br />
D2: Dismantling<br />
and<br />
Dec<strong>on</strong>taminati<strong>on</strong><br />
D4: Panel<br />
"Applying<br />
Less<strong>on</strong>s<br />
Learned from<br />
Past D&D<br />
Activities"<br />
D4: Panel<br />
"Applying<br />
Less<strong>on</strong>s<br />
Learned from<br />
Past D&D<br />
Activities"<br />
8<br />
G1:<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g><br />
Collaborati<strong>on</strong> D3:<br />
Planning<br />
G2: IAEA<br />
Topical for<br />
Disused<br />
Sealed<br />
Radioactive<br />
Sources<br />
(DSRS)<br />
D3:<br />
Planning<br />
H6: Coupled<br />
Process<br />
Modeling and<br />
Natural<br />
Analogues<br />
H6: Coupled<br />
Process<br />
Modeling and<br />
Natural<br />
Analogues<br />
L3: Nuclide<br />
Assay<br />
R2:<br />
Envir<strong>on</strong>mental<br />
Remediati<strong>on</strong><br />
R2:<br />
Envir<strong>on</strong>mental<br />
Remediati<strong>on</strong>
ICEM2010 Technical Sessi<strong>on</strong>s at a Glance<br />
9:00<br />
9:05<br />
9:30<br />
9:55<br />
Room 201 Room 101 Room 406 Room 405 Room 303<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
10:20 - 10:35 Break Break Break Break Break<br />
10:40<br />
11:05<br />
11:30<br />
11:55<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
12:20 - 13:30 Lunch Lunch Lunch Lunch Lunch<br />
13:35<br />
14:00<br />
14:25<br />
14:50<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
15:15 - 15:30 Break Break Break<br />
15:35<br />
16:00<br />
16:25<br />
16:50<br />
17:15<br />
Wednesday, October 6<br />
L6: Waste<br />
Treatment<br />
L6: Waste<br />
Treatment<br />
L7: Storage and<br />
Disposal Facility<br />
H7: Performance<br />
Assessment<br />
Modeling and<br />
Parameters<br />
H7: Performance<br />
Assessment<br />
Modeling and<br />
Parameters<br />
H9: Repository<br />
Engineering and<br />
Dem<strong>on</strong>strati<strong>on</strong><br />
D5:<br />
Measurement<br />
and Estimati<strong>on</strong><br />
D6: Waste<br />
Treatment and<br />
N<strong>on</strong>-Reactor<br />
Preparati<strong>on</strong> Preparati<strong>on</strong> Preparati<strong>on</strong><br />
H9: Repository<br />
Engineering<br />
and<br />
Dem<strong>on</strong>strati<strong>on</strong><br />
D5:<br />
Measurement<br />
and Estimati<strong>on</strong><br />
D6: Waste<br />
Treatment and<br />
N<strong>on</strong>-Reactor<br />
9<br />
H8: Site<br />
Characterizati<strong>on</strong><br />
and Modeling of<br />
Geological<br />
Envir<strong>on</strong>ment (1)<br />
H8: Site<br />
Characterizati<strong>on</strong><br />
and Modeling of<br />
Geological<br />
Envir<strong>on</strong>ment (1)<br />
H10: Site<br />
Characterizati<strong>on</strong><br />
and Modeling of<br />
Geological<br />
Envir<strong>on</strong>ment (2)<br />
H10: Site<br />
Characterizati<strong>on</strong><br />
and Modeling of<br />
Geological<br />
Envir<strong>on</strong>ment (2)<br />
R3: ER<br />
Techniques<br />
R3: ER<br />
Techniques<br />
M2: Public<br />
Involvement
M<strong>on</strong>day, October 4, 2010<br />
OPENING SESSION<br />
M<strong>on</strong>day 09:30 Main C<strong>on</strong>venti<strong>on</strong> Hall<br />
---------------------------------------------------------------------------------------<br />
Opening and Welcome Addresses:<br />
Satoru Tanaka, <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> General Chair<br />
Masanori Aritomi, Technical Program Chair<br />
Anibal L. Taboas, Technical Program Co-Chair, ASME<br />
Plenary Speeches:<br />
Tatsujiro Suzuki, Vice Chairman, Japan Atomic Energy<br />
Commissi<strong>on</strong> (Japan)<br />
“Nuclear Energy Strategy for Sustainable Growth:<br />
Aiming at Green Innovati<strong>on</strong> and Life Innovati<strong>on</strong>”<br />
Dae Y. Chung, Principal Deputy Assistant Secretary for<br />
Envir<strong>on</strong>mental Management, US DOE (USA)<br />
“U.S. Office of Envir<strong>on</strong>mental Management - World<br />
Leaders in Nuclear Cleanup and C<strong>on</strong>structi<strong>on</strong>”<br />
Ho Taek Yo<strong>on</strong>, Senior Vice President, KRMC (Korea Rep.)<br />
“Recent Progress in Radioactive Waste Management in<br />
Korea”<br />
Irena Mele, Head of Waste Technology Secti<strong>on</strong>, Divisi<strong>on</strong> of<br />
Nuclear Fuel Cycle and Waste Technology, IAEA<br />
“Radioactive waste management – achievements, needs<br />
and future expectati<strong>on</strong>s”<br />
SESSION L1: Waste Management<br />
M<strong>on</strong>day 13:30 Room 405<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Miklos Garamszeghy, NWMO (Canada)<br />
and TBD<br />
1. 40081 – Radioactive Waste: Feedback of 40-year<br />
Operati<strong>on</strong>s in France<br />
Michel Dutzer, Gérald Ouzounian, Roberto Miguez,<br />
Jean-Louis Tis<strong>on</strong>, Andra (France)<br />
2. 40227 – ILW Characterisati<strong>on</strong> and Strategy Development<br />
at Chapelcross Power Stati<strong>on</strong>, Dumfriesshire, Scotland<br />
Rob Hodgs<strong>on</strong>, Alastair Stewart, Greg Wotherspo<strong>on</strong>,�<br />
Magnox North � (UK); Vince Cane, Dr Rob Thied,<br />
Nuclear Technologies PLC� (UK)<br />
3. 40226 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Ethics of the Management of Low and<br />
Intermediate Radioactive Wastes Generated by Cernavoda<br />
NPP, a Challenge for the Romanian Specialists.<br />
Gheorghe Barariu, Subsidiary of Technology and<br />
Engineering for Nuclear Objectives (Romania)<br />
4. 40149 – CEA's radioactive waste and unused fuel<br />
inventory - Marcoule site example<br />
Jean-Guy Nokhamz<strong>on</strong>, Marc Butez, Ddaniel Fulleringer,<br />
CEA (France)<br />
——————— Break ———————<br />
5. 40258 – Management of historical waste legacy at NRG<br />
Petten<br />
Renate de Vos, Nuclear Research and C<strong>on</strong>sultancy Group�<br />
(Netherlands)<br />
6. 40031 – Norwegian Support For Regulati<strong>on</strong>s Of<br />
Radioactive Waste Management From Uranium Mining<br />
And Mill Tailings In Central Asia<br />
Tamara Zhunussova, Malgorzata Sneve, Astrid Liland,<br />
Norwegian Radiati<strong>on</strong> Protecti<strong>on</strong> Authority (Norway);<br />
Alexander Kim, Kazakhstan Atomic Energy Committee<br />
Technical Sessi<strong>on</strong>s<br />
10<br />
(Kazakhstan); Ulmas Mirsaidov, Tajikistan Nuclear and<br />
Radiati<strong>on</strong> Safety Agency (Tajikistan);Baigabyl<br />
Tol<strong>on</strong>gutov, Chui Ecological Laboratory of Kyrgiz<br />
Republic (Kyrgiz); Per Strand, Norwegian Radiati<strong>on</strong><br />
Protecti<strong>on</strong> Authority, University of Life Sciences (UMB)<br />
(Norway)<br />
7. 40259 – Strengthening the Nuclear Security System of<br />
Central Radioactive Waste Processing and Storage<br />
Facility at AERE<br />
Abdus Sattar Mollah, Bangladesh Atomic Energy<br />
Commissi<strong>on</strong> (Bangladesh)<br />
SESSION H1: : Nati<strong>on</strong>al and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Programs (1)<br />
M<strong>on</strong>day 13:30 Room 101<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Stratis Vomvoris, Nagra (Switzerland)<br />
and Hiromi Tanabe, RWMC (Japan)<br />
1. 40097 – Overview of NUMO's policy for implementing<br />
safe geological disposal and developing supporting<br />
technologies<br />
Hiroyuki Tsuchi, Kenichi Kaku, Katsuhiko Ishiguro, Akira<br />
Deguchi, Yoshiaki Takahashi, NUMO (Japan)<br />
2. 40150 – Stepwise Site Selecti<strong>on</strong> in Switzerland - Sectoral<br />
Plan: Status and Outlook<br />
Thomas Ernst, Stratis Vomvoris, Markus Fritschi, Nagra<br />
(Switzerland)<br />
3. 40084– Site Selecti<strong>on</strong> for a Geological Disposal in<br />
France: an Approach of C<strong>on</strong>vergence<br />
Gérald� Ouzounian, Roberto Miguez, Jean-Louis Tis<strong>on</strong>,<br />
Andra (France)<br />
SESSION H2: Transportati<strong>on</strong>, Storage and Waste<br />
Treatment<br />
M<strong>on</strong>day 13:30 Room 303<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Hiroshige Kikura, Tokyo Tech (Japan)<br />
and Anibal L. Taboas, ANL (USA)<br />
1. 40155 – Support of the Nuclear Research Institute Rez plc<br />
of the Shipment of Spent Nuclear Fuel from Research<br />
Reactors to the Russian Federati<strong>on</strong> for Reprocessing in<br />
the Frame of the RRRFR Program<br />
Josef Podlaha, Karel Svoboda, Nuclear research<br />
institute plc. (Czech Republic)<br />
2. 40177 – L<strong>on</strong>g Term Storage of Nuclear Spent Fuel as Key<br />
Role of Japan's Nuclear Fuel Cycle until 2100: Cost and<br />
Benefit<br />
Tadahiro Katsuta, Meiji University (Japan)<br />
3. 40285 – TRU Recycling Opti<strong>on</strong>s for increasing Protected<br />
Plut<strong>on</strong>ium Producti<strong>on</strong> of FBR<br />
Sidik Permana, Mitsutoshi Suzuki, JAEA (Japan)<br />
4. 40132 – Transuranic (TRU) Waste Volume Reducti<strong>on</strong><br />
Operati<strong>on</strong> at a Plut<strong>on</strong>ium Facility<br />
Michael Cournoyer, Archie E. Nix<strong>on</strong>, Keith W. Fife,<br />
Arnold M. Sandoval, Vincent E. Garcia, Robert L. Dodge,<br />
LANL (USA)<br />
——————— Break ———————<br />
5. 40247 – Dispositi<strong>on</strong> of Transuranic Residues from<br />
Plut<strong>on</strong>ium Isentropic Compressi<strong>on</strong> Experiment (Pu-ICE).<br />
LA-UR 10-04699.<br />
Kapil Goyal, David M. French, LANL (USA); Betty J.<br />
Humphrey, West<strong>on</strong> Soluti<strong>on</strong>s, Inc. (USA); Jeffry Gluth,<br />
Sandia Nati<strong>on</strong>al Laboratories/NM (USA)<br />
6. 40188 – A Milest<strong>on</strong>e in Vitrificati<strong>on</strong> - the Replacement of<br />
a Hot Metallic Crucible with a Cold Crucible Melter in a<br />
Hot Cell at the La Hague Plant
Sphiee Robert, Benoit Carpentier, SGN (France);<br />
Florence Gassot Guilbert, SGN Service procédé<br />
(France); Sandrine Naline, AREVA (France); Frédéric<br />
Gouyaud, AREVA NC (France); Christophe Girold, CEA<br />
(France)<br />
7. 40265 – Adaptati<strong>on</strong> of CCIM technology for HLW<br />
treatment. Results of research and development.<br />
Vladimir Lebedev, Alexander Kobelev, Fyodor Lifanov,<br />
Sergey Dmitriev, SIA Rad<strong>on</strong> (Russia)<br />
SESSION H3: Panel "Radwaste Human Resource<br />
Development to Support the Nuclear Renaissance"<br />
M<strong>on</strong>day 15:15 Room 101<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Chair: Ian G. McKinley, McKinley C<strong>on</strong>sulting<br />
(Switzerland)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> panel focuses <strong>on</strong> answering three questi<strong>on</strong>s that form the<br />
basis for establishing an efficient and effective human resource<br />
development plan for radioactive waste management:<br />
- what resources do we need and when do we need them?<br />
- how can we assure that these resources will be available<br />
(with emphasis <strong>on</strong> training requirements, especially for<br />
generalists and multidisciplinary coordinators)?<br />
- what infrastructure and procedures need to be made<br />
available with high priority now?<br />
Panelists:<br />
Jo<strong>on</strong>h<strong>on</strong>g Ahn, UCB (USA)<br />
Tomio Kawata, NUMO (Japan)<br />
Ian G. McKinley, McKinley C<strong>on</strong>sulting (Switzerland)<br />
Irena Mele, IAEA<br />
Shawn Smith, US NRC (USA)<br />
SESSION D1 : Nati<strong>on</strong>al and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> D&D<br />
Programs<br />
M<strong>on</strong>day 13:30 Room 406<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Sean Bushart, EPRI (USA) and Satoshi<br />
Yanagihara, JAEA (Japan)<br />
1. 40003 – Westinghouse PWR and BWR Reactor Vessel<br />
Segmentati<strong>on</strong> Experience in Using Mechanical Cutting<br />
Process<br />
Joseph Boucau, Stefan Fallström, Per Segerud, Paul<br />
Kreitman, Westinghouse Electric Belgium (Belgium)<br />
2. 40130 – EPRI Nuclear Power Plant Decommissi<strong>on</strong>ing<br />
Technology Program<br />
Karen Kim, Sean Bushart, Mike Naught<strong>on</strong>, Richard<br />
McGrath, Electrict Power Research Institute (USA)<br />
3. 40253 – Tokai-1 Decommissi<strong>on</strong>ing Project<br />
Keizaburou Yoshino, JAPC (Japan)<br />
4. 40289 – Activities of the OECD/NEA WPDD in the Field<br />
of Decommissi<strong>on</strong>ing�<br />
Claudio Pescatore, Patrick O'Sullivan, OECD/NEA�<br />
—————— Break ———————<br />
5. 40307 – French Decommissi<strong>on</strong>ing Feedback Experience<br />
and Less<strong>on</strong>s Learned<br />
Jean-Guy Nokhamz<strong>on</strong>, CEA (France); Patrick<br />
O'Sullivan, OECD/NEA<br />
6. 40032 – Decommissi<strong>on</strong>ing Planning for Swedish<br />
Operating NPPs � Gunnar Hedin, Mathias Edelborg,<br />
Niklas Bergh, Westinghouse Electric Sweden (Sweden);<br />
Jan Carlss<strong>on</strong>, Fredrik de la Gardie, SKB (Sweden)<br />
7. 40104 – Chernobyl nuclear power plant<br />
Decommissi<strong>on</strong>ing Program<br />
Denys Tkachov, Dmytro Stelmakh, Viktor Kuchinskyy,<br />
Technical Sessi<strong>on</strong>s<br />
11<br />
State Special Enterprise Chernobyl Nuclear Power Plant<br />
(Ukraine)<br />
8. 40273 – C<strong>on</strong>siderati<strong>on</strong>s for Grout Formulati<strong>on</strong>s in<br />
Facility Closures using In Situ Strategies�<br />
John Gladen, Mike Serrato, Chris Langt<strong>on</strong>, Savannah<br />
River Nati<strong>on</strong>al Laboratory (USA); Andy Szilagyi, US<br />
DOE (USA)<br />
SESSION R1: Envir<strong>on</strong>mental Impacts<br />
M<strong>on</strong>day 13:30 Room 202A<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Shinzo Ueta, Mitsubishi Materials<br />
Corporati<strong>on</strong> (Japan) and Dawn Wellman, PNNL (USA)<br />
1. 40298 – Main Results of A Remediati<strong>on</strong> of Uranium- and<br />
CHC-C<strong>on</strong>taminated Groundwater�<br />
Jörg Wörner, S<strong>on</strong>ja Margraf, Walter Hackel,�<br />
RD-Hanau (Germany)<br />
2. 40267 – Biogeochemical Gradients, Waste Site Evoluti<strong>on</strong>,<br />
and Implicati<strong>on</strong>s for Sustained Metal and Radi<strong>on</strong>uclide<br />
Attenuati<strong>on</strong> in Complex Subsurface Envir<strong>on</strong>ments�<br />
Karen Skubal, Justin Marble, Kurt D. Gerdes, US DOE<br />
(USA); Miles Denham, Karen Vangelas, Savannah River<br />
Nati<strong>on</strong>al Laboratory (USA)<br />
3. 40260 – Current Mercury Distributi<strong>on</strong> and Bioavailability<br />
in Floodplain Soils of Lower East Fork Popular Creek,<br />
Oak Ridge, Tennessee, USA�<br />
Fengxiang X. Han, Yi Su, David L. M<strong>on</strong>ts, Mississippi<br />
State University (USA)<br />
4. 40262 – Integrated Strategy to Address Hanford's Deep<br />
Vadose Z<strong>on</strong>e Remediati<strong>on</strong> Challenges�<br />
Mark B. Triplett, Mark D. Freshley, Michael J. Truex,<br />
Dawn Wellman, PNNL (USA); Kurt D. Gerdes, Briant L.<br />
Charb<strong>on</strong>eau, John G. Morse, Robert W. Lober, US DOE<br />
(USA); Glen B. Chr<strong>on</strong>ister, CH2M Hill Plateau<br />
Remediati<strong>on</strong> Company (USA)<br />
—————— Break ———————<br />
5. 40235 – Advanced Remedial Methods for Metals and<br />
Radi<strong>on</strong>uclides in Deep Vadose Z<strong>on</strong>e Envir<strong>on</strong>ments<br />
Dawn Wellman, Shas Mattigod, Ann Miracle, Lir<strong>on</strong>g<br />
Zh<strong>on</strong>g, Danielle Jansik, PNNL (USA); Susan Hubbard,<br />
Yuxin Wu, LBNL (USA); Martin Foote, MSE (USA)<br />
6. 40152 – Water discharge from the Chernobyl NPP cooling<br />
p<strong>on</strong>d: the main challenges of the envir<strong>on</strong>mental protecti<strong>on</strong><br />
during post-rehabilitati<strong>on</strong> period<br />
Dmitri Gudkov, Institute of Hydrobiology (Ukraine)<br />
SESSION M1: Envir<strong>on</strong>mental Management<br />
M<strong>on</strong>day 13:30 Room 202B<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Motoi Kawanishi, CRIEPI (Japan) and<br />
Tadao Tanaka, JAEA (Japan)<br />
1. 40086 – Legacy Management: Turning Liabilities into<br />
Assets<br />
Joe Legare, Eric Ols<strong>on</strong>, S.M. Stoller Corporati<strong>on</strong> (USA)<br />
2. 40270 – Less<strong>on</strong>s Learned in Planning the Canadian<br />
Nuclear Legacy Liabilities Program<br />
Michael Stephens, Sheila M. Brooks, Joan Miller, Robert<br />
Mas<strong>on</strong>, AECL (Canada)<br />
3. 40292 – GIS-Based Decisi<strong>on</strong> Support System for the<br />
Former Semipalatinsk Test Site<br />
Maira Mukusheva, Sergey Baranov, Nati<strong>on</strong>al Nuclear<br />
Center (Kazakhstan)<br />
4. 40218 – RFID Technology for Envir<strong>on</strong>mental<br />
Remediati<strong>on</strong> and Radioactive Waste Management<br />
Hanchung Tsai, Yung Liu, ANL (USA); James Shuler, US
DOE (USA)<br />
—————— Break ———————<br />
5. 40181 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Radioactivity of 3H in Metals by a High<br />
Temperature Furnace and a Liquid Scintillati<strong>on</strong> Counter�<br />
Hee Reyoung Kim, Geun Sik Choi, Sang Yun Park,<br />
Chang Woo Lee, Mo<strong>on</strong> Hee Han, KAERI (Korea Rep.)<br />
6. 40275 – Next Generati<strong>on</strong> Waste Glass Melters in the U.S.<br />
DOE Waste Processing Program�<br />
Steven P. Schneider, Gary Smith, US DOE (USA)<br />
Tuesday, October 5, 2010<br />
SESSION L2: Solidificati<strong>on</strong> and Package (1)<br />
Tuesday 09:00 Room 201<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Miklos Garamszeghy, NWMO (Canada)<br />
and Yoshihiko Horikawa, NEL (Japan)<br />
1. 40021 – Commercializati<strong>on</strong> Project of Ulchin<br />
2.<br />
Vitrificati<strong>on</strong><br />
Hyun-jun Jo, Che<strong>on</strong>-Woo Kim, KHNP (Korea Rep.);<br />
Tae-W<strong>on</strong> Hwang, Nuclear Engineering & Technology<br />
Institure (Korea Rep.)<br />
40023 – Plasma Gasificati<strong>on</strong>/Vitrificati<strong>on</strong> of Wet ILW�<br />
Gary Hanus, John Williams, Matt Zirbes, Phoenix<br />
Soluti<strong>on</strong>s Co. (USA)<br />
3. 40026 – Solidificati<strong>on</strong> of Simulated Liquid Waste of<br />
Primary Loop Resin Eluti<strong>on</strong> Process of PWR<br />
Masamichi Obata, Michitaka Saso, Masaaki Kaneko,<br />
Nobuhito Ogaki, Taichi Horimoto, Toshiba corporati<strong>on</strong>,<br />
Toshikazu Waki, <str<strong>on</strong>g>The</str<strong>on</strong>g> Kansai Electirc Power Co., Inc.<br />
(Japan)<br />
—————— Break ———————<br />
4. 40108 – VUJE Experience with Cementati<strong>on</strong> of Liquid<br />
and Wet Radioactive Waste�<br />
Kamil Kravárik, .Zuzana Holická, Ant<strong>on</strong> Pekár, Milan<br />
Žatkulák, VUJE, Inc. (Slovakia)<br />
5. 40112 – Study of LPOP residue <strong>on</strong> spent-resin<br />
mineralizati<strong>on</strong> and solidificati<strong>on</strong>�<br />
Gen-ichi Katagiri, Morio Fujisawa, Fuji Electric Systems<br />
Co., Ltd. (Japan); Kazuya Sano, Norikazu Higashiura,<br />
JAEA (Japan)<br />
SESSION L3: Nuclide Assay<br />
Tuesday 09:00 Room 303<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: David James, DW James C<strong>on</strong>sulting<br />
(USA) and TBD<br />
1. 40279 – Design of a facility for the automated receipt<br />
inspecti<strong>on</strong> and characterizati<strong>on</strong> of LILW using integrated<br />
n<strong>on</strong>-destructive examinati<strong>on</strong> and assay techniques.<br />
Stephen Halliwell, VJ Technologies Inc. (USA)<br />
2. 40167 – Feasibility Study <strong>on</strong> the Nuclide Analysis of the<br />
Radwaste Drum Using the Spectrum to Dose C<strong>on</strong>versi<strong>on</strong><br />
Factor�<br />
Young-Y<strong>on</strong>g Ji, Dae-Seok H<strong>on</strong>g, Tae-kuk Kim, Woo-Seog<br />
Ryu, KAERI (Korea Rep.)<br />
3. 40255 – Portable N<strong>on</strong>-Destructive Assay Methods for<br />
Screening and Segregati<strong>on</strong> of Radioactive Waste<br />
Alan Simps<strong>on</strong>, Martin Clapham, Stephanie J<strong>on</strong>es, Randy<br />
Lucero, Pajarito Scientific Corporati<strong>on</strong> (UK)<br />
—————— Break ———————<br />
4. 40093 – Alpha radioactivity m<strong>on</strong>itor using i<strong>on</strong>ized air<br />
transportati<strong>on</strong> for large size uranium waste (1) - Large<br />
measurement chamber and evaluati<strong>on</strong> of detecti<strong>on</strong><br />
Technical Sessi<strong>on</strong>s<br />
12<br />
performance –<br />
Susumu Naito, Shuji Yamamoto, Miikio Izumi, Yosuke<br />
Hirata, Yukio Yoshimura, Tatsuyuki Maekawa, Toshiba<br />
Corporati<strong>on</strong> (Japan)<br />
5. 40091 – Alpha Radioactivity M<strong>on</strong>itor using I<strong>on</strong>ized Air<br />
Transport Technology for Large Size Uranium Waste (2) -<br />
Simulati<strong>on</strong> model reinforcement for practical apparatus<br />
design –<br />
Takatoshi Asada, Yosuke Hirata, Susumu Naito, Miikio<br />
Izumi, Yukio Yoshimura, Toshiba Corpoati<strong>on</strong> (Japan)<br />
6. 40111 – Preparati<strong>on</strong> of Reference Materials <strong>on</strong><br />
Radiochemical Analysis for Low-Level Radioactive<br />
Waste Generated from Japan Atomic Energy Agency<br />
Ken-ichiro Ishimori, Yutaka Kameo, Mikio Nakashima,<br />
Kuniaki Takahashi, JAEA (Japan)<br />
SESSION H4: Nati<strong>on</strong>al and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Programs (2)<br />
Tuesday 09:00 Room 101<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Jo<strong>on</strong>h<strong>on</strong>g Ahn, UCB (USA) and Kenichi<br />
Kaku NUMO (Japan)<br />
1. 40213 – U.S. NRC Integrated Spent Fuel Management<br />
Plan<br />
Catherine Haney, Shawn Smith, US NRC (USA)<br />
2. 40116 – Regulatory Research for Geological Disposal of<br />
High-level Radioactive Waste in Japan�<br />
Shinichi Nakayama, JAEA (Japan); Yoshio Watanabe,<br />
AIST (Japan); Masami Kato, JNES (Japan)<br />
3. 40280 – Recent Developments and Trends <strong>on</strong><br />
Requirements Management Systems�<br />
Satoru Suzuki, Hiroyoshi Ueda, Kiyoshi Fujisaki,<br />
Katsuhiko Ishiguro, Hiroyuki Tsuchi, NUMO (Japan);<br />
Stratis Vomvoris, Irina Gaus, Nagra (Switzerland)<br />
——————— Break ———————<br />
4. 40228 – Development of Requirements Management<br />
System of NUMO and practical experience with<br />
development of the database c<strong>on</strong>tents<br />
Satoru Suzuki, Hiroyoshi Ueda, Katsuhiko Ishiguro,<br />
Hiroyuki Tsuchi, Kiyoshi Fujisaki, NUMO (Japan);<br />
Kiyoshi Oyamada, JGC Corporati<strong>on</strong> (Japan); Shoko<br />
Yashio, Obayashi Corporati<strong>on</strong> (Japan)<br />
5. 40231 – Applicati<strong>on</strong> Of Lifecycle Management To Design<br />
of <str<strong>on</strong>g>The</str<strong>on</strong>g> UK Geological Disposal Facility<br />
Henry O'Grady, Malcolm Currie, Pars<strong>on</strong>s<br />
Brinckerhoff Ltd. (UK); Philip Rendell, Radioactive,<br />
Waste Management Directorate (UK)<br />
SESSION D2: Dismantling and Dec<strong>on</strong>taminati<strong>on</strong><br />
Tuesday 09:00 Room 202<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Jean-Guy Nokhamz<strong>on</strong>, CEA (France)<br />
and Mot<strong>on</strong>ori Nakagami, Chubu Electric Power (Japan)<br />
1. 40036 – AREVA NP: Experience in Dismantling and<br />
Packaging of Pressure Vessel and Core Internals<br />
Peter Pillokat, Jan Hendrik Bruhn, AREVA NP GmbH<br />
(Germany)<br />
2. 40102 – Study <strong>on</strong> evaluati<strong>on</strong> models of management data<br />
for decommissi<strong>on</strong>ing of Fugen<br />
Yuji Shibahara, Masanori Izumi, Takashi Nanko, Mitsuo<br />
Tachibana, Tsutomu Ishigami, JAEA (Japan)<br />
3. 40083 – CORD Dec<strong>on</strong>taminati<strong>on</strong> Technologies for<br />
Decommissi<strong>on</strong>ing - A Comprehensive Approach Based <strong>on</strong><br />
Over 30 Years Experience<br />
Christoph Stiepani, AREVA NP GmbH (Germany)<br />
——————— Break ———————
4. 40007 – Chemical Dec<strong>on</strong>taminati<strong>on</strong> for<br />
Decommissi<strong>on</strong>ing (DFD) and DFDX�<br />
R<strong>on</strong>ald Morris, Westinghouse Electric Company (USA)<br />
5. 40127 – Methods for Calculati<strong>on</strong> and Optimisati<strong>on</strong> of<br />
Pers<strong>on</strong>nel Exposure during Planning of Decommissi<strong>on</strong>ing<br />
of Nuclear Installati<strong>on</strong>�<br />
Marek Vasko, Ivan Rehak, DECOM, a.s. (Slovakia);<br />
Vladimir Daniska, DECONTA, a.s. (Slovakia); Vladimir<br />
Necas, Slovak University of Technology in Bratislava<br />
(Slovakia)<br />
SESSION D3: Planning<br />
Tuesday 09:00 Room 405<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Joseph Boucau, Westinghouse Electric<br />
Belgium (Belgium) and Toshihiko Higashi, Kansai Electric<br />
Power (Japan)<br />
1. 40129 – Program Change Management During Nuclear<br />
Power Plant Decommissi<strong>on</strong>ing<br />
Mike Naught<strong>on</strong>, Sean Bushart, Karen Kim, EPRI (USA)<br />
2. 40245 – Status of the Support Researches for the<br />
Regulati<strong>on</strong> of Nuclear Facilities Decommissi<strong>on</strong>ing in<br />
Japan<br />
Yusuke Masuda, Yukihiro Iguchi, Satoru Kawasaki,<br />
Masami Kato, JNES (Japan)<br />
3. 40136 – Decommissi<strong>on</strong>ing Costing Approach Based <strong>on</strong><br />
the Standardised List of Costing Items; Less<strong>on</strong>s Learnt<br />
Vladimir Daniska, Frantisek Ondra, Peter Bezak,<br />
DECONTA, a.s. (Slovakia); Ivan Rehak, Marek Vasko,<br />
Jozef Pritrsky, DECOM a.s. (Slovakia) ; Matej Zachar,<br />
Vladimir Necas, Slovak University of Technology in<br />
Bratislava (Slovakia)<br />
—————— Break ———————<br />
4. 40290 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Outline of Decommissi<strong>on</strong>ing Plan for<br />
Hamaoka Nuclear Power Stati<strong>on</strong> Unit-1 and Unit-2<br />
Yoshifusa Fukuoka, Chubu Electric Power Co., Inc.<br />
(Japan)<br />
5. 40015 – Study <strong>on</strong> Influence of Nuclear Fuel Material<br />
Management and Transfer Scenarios <strong>on</strong><br />
Decommissi<strong>on</strong>ing<br />
Kazuma Mizukoshi, Nuclear Engineering, Ltd. (Japan)<br />
6. 40100 – Dose Assessment for setting of EPZ in<br />
Emergency Plan for Decommissi<strong>on</strong>ing of Nuclear Power<br />
Plant<br />
Hirokazu Minato, Hitachi-GE Nuclear Energy (Japan);<br />
Takatoshi Hattori, CRIEPI (Japan); Toshihiko Higashi,<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Kansai Electric Power Co., Inc. (Japan); Takehiro<br />
Iwata, JAPC (Japan)<br />
7. 40044 – Decommissi<strong>on</strong>ing of Ignalina NPP<br />
Karolis Zemkajus, Algirdas Vaidotas, Radioactive Waste<br />
Management Agency in Lithuania (Lithuania)<br />
SESSION G1 : <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Collaborati<strong>on</strong><br />
Tuesday 09:00 Room 406<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Hiromi Tanabe, RWMC (Japan) and<br />
Robin Heard, IAEA<br />
1. 40118 – Advancing the Use of IAEA Networks in<br />
Radioactive Waste Management: Past Successes, Present<br />
Challenges and Future Opportunities.<br />
Paul Degnan, John Kinker, Irena Mele, Paul J. Dinner,<br />
Horst M<strong>on</strong>ken Fernandes, Ant<strong>on</strong>io Morales, Lumir<br />
Nachmilner, Shaheed Hossain, IAEA<br />
2. 40287 – <str<strong>on</strong>g>The</str<strong>on</strong>g> activities of the OECD/NEA RWMC in the<br />
Field of HLW and SF disposal<br />
Technical Sessi<strong>on</strong>s<br />
13<br />
Claudio Pescatore, OECD/NEA<br />
3. 40147 – Grimsel Test Site - Phase VI Status and Outlook<br />
Ingo Blechschmidt, Sven Peter Teodori, Stratis Vomvoris,<br />
Nagra (Switzerland)<br />
SESSION L4: Solidificati<strong>on</strong> and Package (2)<br />
Tuesday 13:30 Room 201<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Gérald Ouzounian, Andra (France) and<br />
TBD<br />
1. 40299 – Treatment of low level radioactive waste by<br />
plasma: a proven technology?<br />
Jan Deckers, Belgoprocess, NV (Belgium)<br />
2. 40128 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Zwilag Plasma Facility - Five Years of<br />
Successful Operati<strong>on</strong><br />
Walter Heep, Zwilag Interim Storage Facility<br />
(Switzerland)<br />
3. 40293 – Safety Assessment Of Disposal C<strong>on</strong>tainer For<br />
Higher Activity Low Level Waste<br />
Mot<strong>on</strong>ori Nakagami, Seiji Komatsuki, Chubu Electric<br />
Power Co., Inc. (Japan); Kyosuke Fujisawa, Takashi<br />
Nishio, KOBE STEEL, LTD. (Japan); Thomas Quercetti,<br />
André Musolff, Karsten Müller, Federal Institute for<br />
Materials Research and Testing (Germany)<br />
SESSION L5: Recycling and Clearance<br />
Tuesday 15:40 Room 201<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Kapila Fernando, ANSTO (Australia)<br />
and TBD<br />
1. 40223 – NPP Bulk Equipment Dismantling Problems and<br />
Experience<br />
Alexander B. Gelbutovsky, Eugeny V. Balushkin, Jury A.<br />
Epikhin, Alexander V. Troshev, Peter I. Cheremisin,<br />
ECOMET-S JSC (Russia)<br />
2. 40073 – Reuse Of C<strong>on</strong>diti<strong>on</strong>ally Released Radioactive<br />
Materials From NPP Decommissi<strong>on</strong>ing Applied In<br />
Motorway Bridges C<strong>on</strong>structi<strong>on</strong><br />
Michal Panik, Tomas Hrncir, Vladimir Necas, Slovak<br />
University of Technology in Bratislava (Slovakia)<br />
3. 40071 – Modelling of Motorway Tunnels Scenario for<br />
Utilizati<strong>on</strong> of C<strong>on</strong>diti<strong>on</strong>ally Released Radioactive<br />
Materials<br />
Tomas Hrncir, Michal Panik, Vladimir Necas, Slovak<br />
University of Technology in Bratislava (Slovakia)<br />
4. 40117 – Estimate of Clearance Levels for Metal Materials<br />
C<strong>on</strong>taminated with Uranium<br />
Seiji Takeda, Hideo Kimura, JAEA (Japan)<br />
SESSION H5: Panel "Advances in Knowledge<br />
Management for Radioactive Waste Disposal"<br />
Tuesday 13:30 Room 101<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Hiroyuki Umeki, Hitoshi Makino, JAEA<br />
(Japan) and Ian G. McKinley, McKinley C<strong>on</strong>sulting<br />
(Switzerland)<br />
Part 1: Status and plans of KM activities in nati<strong>on</strong>al<br />
programmes<br />
Informati<strong>on</strong> exchange with emphasis <strong>on</strong> identificati<strong>on</strong> of<br />
potential areas for collaborati<strong>on</strong>. Panelists represent<br />
implementing organisati<strong>on</strong>s, regulatory authorities and R&D<br />
organisati<strong>on</strong>s, thus bringing different perspectives <strong>on</strong> KM.<br />
Part 2: Brainstorming <strong>on</strong> advanced KM tools
A comm<strong>on</strong> requirement in all geological disposal programmes<br />
is efficiently and rigorously managing increasing large and<br />
complex fluxes of informati<strong>on</strong>. Emphasis will be <strong>on</strong> suggesting<br />
practical applicati<strong>on</strong>s and further improvements of advanced<br />
KM tools that have been developed by JAEA, distinguishing<br />
between programme-specific c<strong>on</strong>straints and more generic areas,<br />
which could be a focus for future collaborative projects.<br />
Panelists:<br />
Johan Anderss<strong>on</strong>, JA Streamflow (Sweden)<br />
Kenzi Karasaki, LBNL (USA)<br />
Masami Kato, JNES (Japan)<br />
Lawrence Kokajko, US NRC (USA)<br />
Mark Nutt, ANL (USA)<br />
Richard Shaw, BGS (UK)<br />
Hiroyuki Tsuchi, NUMO (Japan)<br />
Hiroyuki Umeki, JAEA (Japan)<br />
SESSION H6: Coupled Process Modeling and Natural<br />
Analogues<br />
Tuesday 13:30 Room 405<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Irina Gaus, Nagra (Switzerland) and<br />
Gento Kamei, JAEA (Japan)<br />
1. 40306 Keynote – A Discussi<strong>on</strong> of Key Issues in Coupled<br />
THM Processes in Clays, Rock Salt and Crystalline Rock<br />
with Bent<strong>on</strong>ite Buffer<br />
Chin-Fu Tsang, LBNL (USA)<br />
2. 40159 – Envir<strong>on</strong>mental Remediati<strong>on</strong> of High-Level<br />
Nuclear Waste in Geological Repository: Modified<br />
Computer Code Creates Ultimate Benchmark in Natural<br />
systems<br />
Geoffrey Peter, Oreg<strong>on</strong> Institute of Technology Portland<br />
Center (USA)<br />
3. 40196 – Effect of the Residual Heat Release of the<br />
Nuclear Waste Stored in an Unsaturated Z<strong>on</strong>e <strong>on</strong><br />
Radi<strong>on</strong>uclide Release<br />
Lubna K. Hamdan, John C. Walt<strong>on</strong>, Arturo Woocay,<br />
University of Texas at El paso (USA)<br />
4. 40072 – Evaluati<strong>on</strong> of behavior of rare earth elements<br />
based <strong>on</strong> determinati<strong>on</strong> of chemical state in groundwater<br />
in granite<br />
Yuhei Yamamoto, Daisuke Aosai, Takashi Mizuno, JAEA<br />
(Japan)<br />
—————— Break ———————<br />
5. 40022 – Natural analogue studies of bent<strong>on</strong>ite reacti<strong>on</strong><br />
under hyperalkaline c<strong>on</strong>diti<strong>on</strong>s: overview of <strong>on</strong>going<br />
work at the Zambales Ophiolite, Philippines<br />
Naoki Fujii, M. Yamakawa, RWMC (Japan); K. Namiki,<br />
Obayashi Corporati<strong>on</strong> (Japan); T. Sato, Hokkaido<br />
University (Japan); N. Shikaz<strong>on</strong>o, Keio University<br />
(Japan); C. A. Arcilla, C. Pascua, University of the<br />
Philippines (Philippines); W Russell Alexander,<br />
Bedrock Geosciences ( Switzerland)<br />
6. 40063 – Natural Analogues of Cement: Overview of the<br />
Unique Systems in Jordan<br />
Gento Kamei, JAEA (Japan); W Russell Alexander,<br />
Bedrock Geosciences (Switzerland); Ian D. Clark,<br />
University of Ottawa (Canada); Paul Degnan, IAEA;<br />
Marcel Elie, Shell (Netherlands); Hani Khoury, Elias<br />
Salameh, University of Jordan (Jordan), Ant<strong>on</strong>i E.<br />
Milodowski, British Geological Survey (UK), Alister F.<br />
Pitty, Pitty C<strong>on</strong>sulting � (UK); John A.T. Smellie,<br />
C<strong>on</strong>terra (Sweden)<br />
Technical Sessi<strong>on</strong>s<br />
14<br />
SESSION D4: Panel "Applying Less<strong>on</strong>s Learned from<br />
Past D&D Activities"<br />
Tuesday 13:30 Room 202<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Koji Okamoto, University of Tokyo<br />
(Japan) and Claudio Pescatore, OECD/NEA<br />
In this panel, internati<strong>on</strong>al less<strong>on</strong>s learned from past D&D<br />
activities will be discussed to optimize future decommissi<strong>on</strong>ing<br />
activities. Each panelist will talk about some of topics below.<br />
Discussi<strong>on</strong> will be focused <strong>on</strong> two or three topics. Later in the<br />
panel, a recent TV report in Japan will be introduced to discuss<br />
mass media issue, too.<br />
a. Decommissi<strong>on</strong>ing Project Management<br />
b. Decommissi<strong>on</strong>ing Techniques<br />
c. Waste Disposal<br />
d. Building and Site Remediati<strong>on</strong><br />
e. Social Issues and Others<br />
Panelists:<br />
Koji Okamoto, Keynote, University of Tokyo (Japan)<br />
Sean Bushart, EPRI (USA)<br />
Satoshi Karigome, JAPC (Japan)<br />
Jean-Guy Nokhamz<strong>on</strong>, CEA (France)<br />
Claudio Pescatore, OECD/NEA<br />
Andy Szilagyi, US DOE (USA)<br />
Satoshi Yanagihara, JAEA (Japan)<br />
SESSION R2: Envir<strong>on</strong>mental Remediati<strong>on</strong><br />
Tuesday 13:30 Room 303<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Hirofumi Tsukada, Institute for<br />
Envir<strong>on</strong>mental Sciences (Japan) and Jörg Wörner,<br />
RD-Hanau (Germany)<br />
1. 40261 – Reclamati<strong>on</strong> of Three In Situ Uranium Mines -<br />
Innovative Techniques<br />
Wallace Mays, W M Mining Company (USA)<br />
2. 40005 – Envir<strong>on</strong>mental remediati<strong>on</strong> Activities at the<br />
Ningyo-toge Uranium Mine, Japan<br />
Hiroshi Saito, Tomihiro Taki, JAEA (Japan)<br />
3. 40092 – Rad<strong>on</strong> impact at a remediated uranium mine site<br />
in Japan<br />
Yuu Ishimori, JAEA (Japan)<br />
4. 40243 – Phosphate based remediati<strong>on</strong> techniques:<br />
interacti<strong>on</strong> of phosphate with uranium-bound calcite<br />
Chase Bovaird, Dawn Wellman, PNNL (USA)<br />
—————— Break ———————<br />
5. 40220 – Remediati<strong>on</strong> of Old Envir<strong>on</strong>mental Liabilities in<br />
the Nuclear Research Institute Rez plc<br />
Karel Svoboda, Josef Podlaha, Nuclear Research Institute<br />
Rez plc (Czech Republic)<br />
SESSION G2: IAEA Topical for Disused Sealed<br />
Radioactive Sources (DSRS)<br />
Tuesday 13:30 Room 406<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Hiromi Tanabe, RWMC (Japan) and<br />
Irena Mele, IAEA<br />
1. 40028 – <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> initiatives addressing the safety and<br />
security of Disused Sealed Radioactive Sources (DSRS)<br />
Robin Heard, IAEA<br />
2. 40303 – Current situati<strong>on</strong> and Management Plan of<br />
Radioactive Sources in Japan<br />
Hirokuni Ito, Tadashi Ishii, Tomokazu Ueta, Takao<br />
Nakaya, Kenya Suyama, MEXT (Japan)
3. 40060 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Deployment of the Mobile Hot Cell to<br />
C<strong>on</strong>diti<strong>on</strong> High Activity Disused Sealed Radioactive<br />
Sources (DSRS) for L<strong>on</strong>g Term Storage or Removal<br />
Gerhardus R. Liebenberg, South African Nuclear Energy<br />
Corporati<strong>on</strong> (Necsa) (South Africa)<br />
4. 40266 – Problems with Packaged Sources in Foreign<br />
Countries<br />
James Matzke, John Zarling, Cristy Abeyta, Joseph A.<br />
Tompkins, LANL (USA)<br />
—————— Break ———————<br />
5. 40085 – <str<strong>on</strong>g>The</str<strong>on</strong>g> IAEA's approach to the security of<br />
radioactive material<br />
Robin Heard, IAEA<br />
6. 40058 – Radioactive Waste Management in Leban<strong>on</strong><br />
Munzna Assi, Lebanese Atomic Energy Commissi<strong>on</strong><br />
(Leban<strong>on</strong>)<br />
7. 40029 – <str<strong>on</strong>g>The</str<strong>on</strong>g> ultimate soluti<strong>on</strong> – disposal of Disused<br />
Sealed Radioactive Sources (DSRS)<br />
Robin Heard, IAEA<br />
Wednesday, October 6, 2010<br />
SESSION L6: Waste Treatment<br />
Wednesday 09:00 Room 201<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Gérald Ouzounian, Andra (France) and<br />
Hirokazu Tanaka, Mitsubishi Materials Corporati<strong>on</strong><br />
(Japan)<br />
1. 40055 – Drying System For Radioactivated Metal Waste<br />
From Nuclear Power Stati<strong>on</strong><br />
Nobuhito Ogaki, Yasushi Ooishi, Hir<strong>on</strong>ori Takabayashi,<br />
Masamichi Obata, Taichi Horimoto, Toshiba Corporati<strong>on</strong><br />
(Japan)<br />
2. 40186 – Macroporous Catalysts for Hydrothermal<br />
Oxidati<strong>on</strong> of Metallorganic Complexes at Liquid<br />
Radioactive Waste Treatment<br />
Valentin Avramenko, Dmitry Marinin, Vitaly Mayorov,<br />
Alexander Mir<strong>on</strong>enko, Marina Palamarchuk, Valentin<br />
Sergienko, Institute of Chemistry FEDRAS (Russia)<br />
3. 40157 – Carb<strong>on</strong>aceous radioactive waste treatment<br />
Gerard Laurent, EDF/CIDEN (France)<br />
—————— Break ———————<br />
4. 40163 – Impermeable graphite: A new development for<br />
the waste management of irradiated graphite<br />
Johannes Fachinger, Karl-Heinz Grosse, Furnances<br />
Nuclear Applicati<strong>on</strong>s Grenoble (Germany); Richard<br />
Seemann, Milan Hrovat ALD (Germany)<br />
5. 40165 – THOR® Steam Reforming Technology for the<br />
Treatment of I<strong>on</strong> Exchange Resins and More Complex<br />
Wastes such as Fuel Reprocessing Wastes<br />
J. Brad Mas<strong>on</strong>, Corey Myers, Studsvik, Inc. (USA)<br />
6. 40257 – Phase Behavior and Reverse Micelle Formati<strong>on</strong><br />
in Supercritical CO2 with DTAB and F-pentanol for<br />
Dec<strong>on</strong>taminati<strong>on</strong> of Radioactive Wastes<br />
Kensuke Kurahashi, Osamu Tomioka, Yoshihiro Meguro,<br />
JAEA (Japan)<br />
SESSION H7: Performance Assessment Modeling and<br />
Parameters<br />
Wednesday 09:00 Room 101<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Hiroyuki Umeki, JAEA (Japan) and<br />
Masaki Tsukamoto, CRIEPI (Japan)<br />
Technical Sessi<strong>on</strong>s<br />
15<br />
1. 40305 Keynote – Development of a Realistic Repository<br />
Performance Assessment Method<br />
Jo<strong>on</strong>h<strong>on</strong>g Ahn, UCB (USA)<br />
2. 40204 – Integrated model for the near field of a repository<br />
in granite host-rock. Probabilistic approach<br />
Lara Duro, Alba Valls, Olga Riba, Jordi Bruno, Amphos<br />
XXI C<strong>on</strong>sulting S.L.(Spain); Aurora Martinez-Esparza,<br />
ENRESA (Spain)<br />
3. 40017 – Spatial Variability and Parametric Uncertainty in<br />
Performance Assessment Models<br />
Osvaldo Pensado, James Mancillas, Scott Painter,<br />
Southwest Research Institute (USA); Yasuo Tomishima,<br />
AIST (Japan)<br />
—————— Break ———————<br />
4. 40203 – Development of a Radiolytic Model for the<br />
Alterati<strong>on</strong> of Spent Nuclear Fuel. Incorporati<strong>on</strong> of<br />
n<strong>on</strong>-oxidative matrix dissoluti<strong>on</strong> and hydrogen<br />
oxidati<strong>on</strong> inhibiti<strong>on</strong> effect<br />
Lara Duro, Alba Valls, Olga Riba, Jordi Bruno, Amphos<br />
XXI C<strong>on</strong>sulting S.L.(Spain); Aurora Martinez-Esparza,<br />
ENRESA (Spain)<br />
5. 40172 – Evaluated and Estimated Solubility of Some<br />
Elements for Performance Assessment of Geological<br />
Disposal of High-level Radioactive Waste Using Updated<br />
Versi<strong>on</strong> of <str<strong>on</strong>g>The</str<strong>on</strong>g>rmodynamic Database<br />
Akira Kitamura, Reisuke Doi, JAEA (Japan); Yasushi<br />
Yoshida, Inspecti<strong>on</strong> Development Co., Ltd. (Japan)<br />
6. 40049 – C<strong>on</strong>siderati<strong>on</strong> <strong>on</strong> Soil Origin Carb<strong>on</strong> Transfer to<br />
Leafy Vegetables Using Stable Carb<strong>on</strong> Isotope Ratios<br />
Keiko Tagami, Shigeo Uchida, Nati<strong>on</strong>al Institute of<br />
Radiological Sciences (Japan)<br />
7. 40050 – Comparis<strong>on</strong> of Soil-to-plant Transfer Factors for<br />
Rice and Wheat Grains<br />
Shigeo Uchida, Keiko Tagami, Nati<strong>on</strong>al Institute of<br />
Radiological Sciences (Japan)<br />
SESSION H8: Site Characterizati<strong>on</strong> and Modeling of<br />
Geological Envir<strong>on</strong>ment (1)<br />
Wednesday 09:00 Room 405<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Chin-Fu Tsang, LBNL (USA) and Motoi<br />
Kawanishi, CRIEPI (Japan)<br />
1. 40121 – Development of Characterizati<strong>on</strong> Methodology<br />
for Fault Z<strong>on</strong>e Hydrology<br />
Kenzi Karasaki, LBNL (USA); Tiemi Onishi US<br />
Geological Survey (USA); Erika Gasperikova LBNL<br />
(USA) Junichi Goto, Tadashi Miwa, Hiroyuki Tsuchi,<br />
NUMO (Japan); Keiichi Ueta, Kenzo Kiho, Kimio<br />
Miyakawa, CRIEPI (Japan)<br />
2. 40189 – An attempt to evaluate horiz<strong>on</strong>tal crustal<br />
movement by geodetic and geological approach in the<br />
Hor<strong>on</strong>obe area, northern Hokkaido, Japan<br />
Tetsuya Tokiwa, Koichi Asamori, Tadafumi Niizato,<br />
Tsuyoshi Nohara, JAEA (Japan); Yuki Matsuura, Hitachi<br />
Zosen Co., Ltd. (Japan); Hideki Kosaka, Kankyo<br />
Chishitsu Co., Ltd. (Japan)<br />
3. 40054 – Relati<strong>on</strong>ship between hypocentral distributi<strong>on</strong><br />
and geological structure in the Hor<strong>on</strong>obe area, northern<br />
Hokkaido, Japan<br />
Tetsuya Tokiwa, Koichi Asamori, Naoto Hiraga, Osamu<br />
Yamada, Hideharu Yokota, JAEA (Japan); Hirokazu<br />
Moriya, Tohoku University (Japan); Hikaru Hotta, Itaru<br />
Kitamura, C<strong>on</strong>structi<strong>on</strong> Project C<strong>on</strong>sultants, Inc. (Japan)<br />
—————— Break ———————<br />
4. 40062 – Technical know-how for modeling of geological<br />
envir<strong>on</strong>ment (1) Overview and groundwater flow
modeling<br />
Hiromitsu Saegusa, Shinji Takeuchi, Keisuke Maekawa,<br />
Hideaki Osawa, Takeshi Semba, JAEA (Japan)<br />
5. 40066 – Technical Know-how For Modeling Of<br />
Geological Envir<strong>on</strong>ment (2) Geological Modeling<br />
Toshiyuki Matsuoka, Kenji Amano, Hideaki Osawa,<br />
Takeshi Semba, JAEA (Japan)<br />
6. 40039 – <str<strong>on</strong>g>The</str<strong>on</strong>g> l<strong>on</strong>g-term stability of geological<br />
envir<strong>on</strong>ments in the various rock types in Japan from the<br />
perspective of uranium mineralizati<strong>on</strong><br />
Eiji Sasao, JAEA (Japan)<br />
SESSION D5: Measurement and Estimati<strong>on</strong><br />
Wednesday 09:00 Room 406<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Vladimir Daniska, DECONTA, a.s.<br />
(Slovakia) and Yukihiko Iguchi, JNES (Japan)<br />
1. 40045 – Improvement of Radioactivity Inventory<br />
Evaluati<strong>on</strong> Procedure In Preparatory Tasks for<br />
Decommissi<strong>on</strong>ing<br />
Ken-ichi Tanaka, Hidenori Tanabe, Hideaki Ichige,<br />
JAPC (Japan)<br />
2. 40202 – Verificati<strong>on</strong> of Source Term Analysis System for<br />
Decommissi<strong>on</strong>ing Wastes from CANDU Reactor<br />
D<strong>on</strong>g-Keun Cho, Gwang-Min Sun, J<strong>on</strong>gw<strong>on</strong> Choi,<br />
KAERI (Korea Rep.); D<strong>on</strong>ghyeun Hwang, Hak-Soo Kim,<br />
Tae-W<strong>on</strong> Hwang, KHNP (Korea Rep.)<br />
3. 40294 – Evaluati<strong>on</strong> of <str<strong>on</strong>g>The</str<strong>on</strong>g> Activated Radioactivity of<br />
Turbine Equipments in BWR<br />
Masato Watanabe, Mot<strong>on</strong>ori Nakagami, Chubu Electric<br />
Power Co., Inc. (Japan)<br />
—————— Break ———————<br />
4. 40014 – Optimizati<strong>on</strong> of Quantitative Waste Volume<br />
Determinati<strong>on</strong> Technique for Hanford Waste Tank<br />
Closure<br />
Yi Su, David L. M<strong>on</strong>ts, Ping-Rey Jang, Zhiling L<strong>on</strong>g,<br />
Walter P. Okhuysen, Olin P. Nort<strong>on</strong>, Lawrence L.<br />
Gresham, Jeffrey S. Lindner, Mississippi State University<br />
(USA)<br />
5. 40120 – Implementati<strong>on</strong> of Decommissi<strong>on</strong>ing Materials<br />
C<strong>on</strong>diti<strong>on</strong>al Clearance Process to the OMEGA<br />
Calculati<strong>on</strong> Code<br />
Matej Zachar, Vladimir Necas, Slovak University of<br />
Technology (Slovakia); Vladimir Daniska� DECONTA�<br />
a.s. (Slovakia)<br />
6. 40183 – Quantitative determinati<strong>on</strong> of the initial<br />
comp<strong>on</strong>ents in the activated pressure tubes of the<br />
Wols<strong>on</strong>g 1st CANDU reactor<br />
Gwang-Min Sun, D<strong>on</strong>g-Keun Cho, KAERI (Korea Rep.)<br />
SESSION R3: ER Techniques<br />
Wednesday 09:00 Room 303<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Takumi Kubota, Kyoto University<br />
Research Reactor Institute (Japan) and Mark B. Triplett,<br />
PNNL (USA)<br />
1. 40286 – Sequential Extracti<strong>on</strong> and Determinati<strong>on</strong> of<br />
Depleted Uranium in the Presence of Natural Uranium in<br />
Envir<strong>on</strong>mental Soil samples by ICP-MS<br />
Mohamed Amr, Alaa E. Negmeldin, Khalid Al-Saad, A. T.<br />
Al-Kinani, Qatar University (Qatar); A. I. Helal, Atomic<br />
Energy Authority (Qatar)<br />
2. 40096 – Determinati<strong>on</strong> of Envir<strong>on</strong>mental Uranium<br />
C<strong>on</strong>centrati<strong>on</strong> by Utilizing Gamma-ray Emissi<strong>on</strong> from<br />
the Progeny Radi<strong>on</strong>uclides<br />
Technical Sessi<strong>on</strong>s<br />
16<br />
Tadao Tanaka, Taro Shimada, Takenori Sukegawa, JAEA<br />
(Japan); Takeshi Ito, Japan ATOX Co., Ltd. (Japan)<br />
3. 40170 – Natural Radioactivity Levels And Gamma-Ray<br />
Dose Rate In Soil And Transfer Of Radi<strong>on</strong>uclides From<br />
Soil To Vegetati<strong>on</strong> Of Some Northern Area Of Pakistan<br />
Using Gamma-Ray Spectrometry<br />
Muhammad Ismail, Hasan M.Khan, Peshawar<br />
University (Pakistan); Khalid Khan, Pinstech Islamabad<br />
(Pakistan)<br />
—————— Break ———————<br />
4. 40034 – Effect of Fertilizer and Soil Amendments <strong>on</strong><br />
Extracti<strong>on</strong> Yields of Radioiodine and Radiocesium in Soil<br />
Hirofumi Tsukada, Akira Takeda, Shunichi Hisamatsu,<br />
Institute for Envir<strong>on</strong>mental Sciences (Japan)<br />
5. 40246 – Impact of Mobile-Immobile Water Domains <strong>on</strong><br />
the Retenti<strong>on</strong> of Technetium (Tc-99) in the Vadose Z<strong>on</strong>e<br />
Danielle Jansik, Dawn Wellman, Elsa Cordova, PNNL<br />
(USA)<br />
6. 40207 – Nano Technologies for Envir<strong>on</strong>mental<br />
Remediati<strong>on</strong><br />
Harch Gill, Lehigh Nanotech (USA)<br />
7. 40122 – Remediati<strong>on</strong> of 153Gd-c<strong>on</strong>taminated sand by<br />
fulvic and humic materials extracted from fallen cherry<br />
leaves<br />
Takumi Kubota, Kyoto University Research Reactor<br />
Institute (Japan)<br />
SESSION L7: Storage and Disposal Facility<br />
Wednesday 13:30 Room 201<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Sheila M. Brooks, AECL (Canada) and<br />
TBD<br />
1. 40095 – Design, Licensing and Commissi<strong>on</strong>ing Activities<br />
for the Waste Storage Facility to Manage the Waste<br />
Streams from Retubing of Wols<strong>on</strong>g-1 CANDU 600 MW<br />
Nuclear Generating Stati<strong>on</strong> in South Korea<br />
Nikos P<strong>on</strong>tikakis, John Ballantine, Shar<strong>on</strong> Hugh, Joulien<br />
Moussalam, AECL (Canada)<br />
2. 40284 – Microbial Occurrence in Bent<strong>on</strong>ite-based Buffer<br />
Materials of a Final Disposal Site for Low Level<br />
Radioactive Waste in Taiwan<br />
F<strong>on</strong>g-In Chou, Chia-Chin Li, Tzung-Yuang Chen,<br />
Nati<strong>on</strong>al Tsing Hua University (Taiwan); Hsiao-Wei Wen,<br />
Nati<strong>on</strong>al Chung Hsing University (Taiwan)<br />
3 40153 – Assessing the gas transport mechanisms in the<br />
Swiss L/ILW c<strong>on</strong>cept using numerical modeling<br />
Irina Gaus, Paul Marschall, Joerg Rueedi, Nagra<br />
(Switzerland); Rainer Senger, John Ewing, Intera Inc.<br />
Swiss Branch (Switzerland)<br />
4. 40283 – <str<strong>on</strong>g>The</str<strong>on</strong>g> progress and results of Dem<strong>on</strong>strati<strong>on</strong> Test<br />
of Cavern-Type Disposal Facility<br />
Yoshihiro Akiyama, Kenji Terada, Nobuaki Oda, Tsutomu<br />
Yada, Takahiro Nakajima, RWMC (Japan)<br />
SESSION H9: Repository Engineering and<br />
Dem<strong>on</strong>strati<strong>on</strong><br />
Wednesday 13:30 Room 101<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Ian G. McKinley, McKinley C<strong>on</strong>sulting<br />
(Switzerland) and Hidekazu Asano, RWMC (Japan)<br />
1. 40304 Keynote – Repository engineering and<br />
dem<strong>on</strong>strati<strong>on</strong>: special challenges for TRU<br />
Ian G. McKinley, McKinley C<strong>on</strong>sulting (Switzerland)<br />
2. 40119 – Half-Scale Test: An important step to<br />
dem<strong>on</strong>strate the feasibility of the Belgian Superc<strong>on</strong>tainer
c<strong>on</strong>cept for disposal of HLW<br />
Lou Areias, SCK CEN and VUB (Belgium); Bart Craeye,<br />
Ghent University/Artesis Hogeschool Antwerpen<br />
(Belgium); Geert De Schutter, Ghent University<br />
(Belgium); Hughes Van Humbeeck, William Wacquier,<br />
ONDRAF/NIRAS (Belgium); Alain Van Cotthem, Loic<br />
Villers Technum-Tractebel (Belgium)<br />
3. 40175 – Full-Scale Test <strong>on</strong> Overpack Closure Techniques<br />
for HLW Repository Operati<strong>on</strong> - Welding Methods and<br />
UT Systems For L<strong>on</strong>g-Term Structural Integrity of the<br />
Weld Joint -<br />
Ario Nakamura, Hidekazu Asano, RWMC (Japan);<br />
Takashi Furukawa, JAPAN POWER ENGINEERING<br />
AND INSPECTION CORPORATION (Japan); Kyosuke<br />
Fujisawa, KOBE STEEL, LTD. (Japan); Susumu<br />
Kawakami, IHI Corporati<strong>on</strong> (Japan); Takashi Ito,<br />
Mitsubishi Heavy Industries, Ltd. (Japan)<br />
4. 40242 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong><br />
Technology, (I) Dem<strong>on</strong>strati<strong>on</strong> and Evaluati<strong>on</strong> of<br />
Remote Handling Technologies<br />
Hitoshi Nakashima, Hidekazu Asano, RWMC (Japan);<br />
Hideki Kawamura, Obayashi Corporati<strong>on</strong> (Japan)<br />
—————— Break ———————<br />
5. 40251 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong><br />
Technology, (II) Bent<strong>on</strong>ite Block Forming and Vertical<br />
Emplacement/JGC<br />
Hajime Takao, Tatsuhiro Takegahara JGC Corporati<strong>on</strong><br />
(Japan); Hitoshi Nakashima, Hidekazu Asano, RWMC<br />
(Japan)<br />
6. 40268 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong><br />
Technology, (III) Transportati<strong>on</strong> and Horiz<strong>on</strong>tal<br />
Emplacement of Pre-Fabricated EBS Module (PEM)<br />
Susumu Kawakami, IHI Corporati<strong>on</strong> (Japan); Hitoshi<br />
Nakashima, Hidekazu Asano, RWMC (Japan)<br />
7. 40236 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong><br />
Technology, (IV) Shotclay Technique for Seamless<br />
C<strong>on</strong>structi<strong>on</strong> of EBS<br />
Ichizo Kobayashi, Soh Fujisawa, Makoto Nakajima,<br />
Masaru Toida, Kajima Corporati<strong>on</strong> (Japan); Hitoshi<br />
Nakashima, Hidekazu Asano, RWMC (Japan)<br />
8. 40254 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong><br />
Technology, (V) Preliminary Study and Small Scale<br />
Experiments <strong>on</strong> the Method of Removal of Buffer<br />
Material with Salt Soluti<strong>on</strong><br />
Satohito Toguri, Jiho Jang, Takashi Ishii, Mitsunobu<br />
Okihara, Kengo Iwasa, SHIMIZU CORPORATION<br />
(Japan); Hitoshi Nakashima, Hidekazu Asano, RWMC<br />
(Japan)<br />
SESSION H10: Site Characterizati<strong>on</strong> and Modeling of<br />
Geological Envir<strong>on</strong>ment (2)<br />
Wednesday 13:30 Room 405<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Kenji Karasaki, LBNL (USA) and Yuji<br />
Ijiri, Taisei Corporati<strong>on</strong> (Japan)<br />
1. 40135 – Dry-run of Site Investigati<strong>on</strong> Planning using the<br />
Manual for Preliminary Investigati<strong>on</strong> in Japan<br />
Shigeki Akamura, Tadashi Miwa, NUMO (Japan);<br />
Tatsuya Tanaka, Obayashi Corporati<strong>on</strong> (Japan); Hiroshi<br />
Shiratsuchi, Tokyo Electric Power Service Co.,ltd.<br />
(Japan); Atsushi Horio, DIA CONSULTANTS CO., Ltd.<br />
(Japan)<br />
2. 40070 – Evaluati<strong>on</strong> of the l<strong>on</strong>g-term evoluti<strong>on</strong> of the<br />
groundwater system in the Mizunami area, Japan<br />
Takashi Mizuno, Teruki Iwatsuki, JAEA (Japan); Ant<strong>on</strong>i<br />
E. Milodowski, British Geological Survey (UK)<br />
Technical Sessi<strong>on</strong>s<br />
17<br />
3. 40077 – Study <strong>on</strong> the Estimati<strong>on</strong> Error Caused by Using<br />
One-dimensi<strong>on</strong>al Model for the Evaluati<strong>on</strong> of Dipole<br />
Tracer Test<br />
Yuji Ijiri, Yumi Naemura, Taisei Corporati<strong>on</strong> (Japan);<br />
Kenji Amano, Keisuke Maekawa, Kunio Ota, Takanori<br />
Kunimaru, Atsushi Sawada, JAEA (Japan)<br />
4. 40056 – Development of Comprehensive Techniques for<br />
Coastal Site Characterisati<strong>on</strong> (1) Strategic Overview<br />
Kunio Ota, Kenji Amano, Tadafumi Niizato, JAEA<br />
(Japan); W Russell Alexander, Bedrock Geosciences<br />
(Switzerland); Yoshiaki Yamanaka, Suncoh C<strong>on</strong>sultants<br />
(Japan)<br />
—————— Break ———————<br />
5. 40052 – Development of comprehensive techniques for<br />
coastal site characterisati<strong>on</strong>: (3) C<strong>on</strong>ceptualisati<strong>on</strong> of<br />
l<strong>on</strong>g-term geosphere evoluti<strong>on</strong><br />
Tadafumi Niizato, Kenji Amano, Kunio Ota, Takanori<br />
Kunimaru, JAEA (Japan); Lany<strong>on</strong> Bill, Nagra<br />
(Switzerland); W Russell Alexander, Bedrock<br />
Geosciences (Switzerland)<br />
6. 40048 – Development of Comprehensive Techniques for<br />
Coastal Site Characterisati<strong>on</strong> (2) Integrated<br />
Palaeohydrogeological Approach for Development of Site<br />
Evoluti<strong>on</strong> Models<br />
Kenji Amano, Tadafumi Niizato, Hideharu Yokota, Kunio<br />
Ota, JAEA (Japan); Bill Lany<strong>on</strong>, Nagra (Switzerland); W<br />
Russell Alexander, Bedrock Geosciences (Switzerland)<br />
7. 40041 – Development of Methodology of Groundwater<br />
Flow and Solute Transport Analysis in the Hor<strong>on</strong>obe Area,<br />
Hokkaido, Japan<br />
Keisuke Maekawa, Hitoshi Makino, Hiroshi Kurikami,<br />
Tadafumi Niizato, Manabu Inagaki, Makoto Kawamura,<br />
JAEA (Japan)<br />
SESSION D6: Waste Treatment and N<strong>on</strong>-Reactor<br />
Wednesday 13:30 Room 406<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Co-Chairs: Takeshi Ishikura, IAE (Japan) and<br />
Hitoshi Sakai, Toshiba Corporati<strong>on</strong> (Japan)<br />
1. 40105 – Estimati<strong>on</strong> of Radioactivity of Graphite Blocks<br />
in Tokai Power Stati<strong>on</strong> using Statistical Method<br />
Masaaki Nakano, Fuji Electric Holdings Co., Ltd.<br />
(Japan); Hisashi Mikami, Fuji Electric Systems Co., Ltd.<br />
(Japan); Hideaki Ichige, Shinich Tsukada, JAPC<br />
(Japan)<br />
2. 40115 – <str<strong>on</strong>g>The</str<strong>on</strong>g> treatment of hexavalent chromium in waste<br />
liquid from Fugen Decommissi<strong>on</strong>ing<br />
Yuki Yahiro, Seiji Yamamoto, Koji Negishi, Hitoshi Sakai,<br />
Tadashi Fukushima, Norimasa Yoshida, Toshiba<br />
Corporati<strong>on</strong> (Japan); Nobuo Ishizuka, Yuji Sato, Wataru<br />
Fujiwara, JAEA (Japan)<br />
3. 40201 – Characterizati<strong>on</strong> of Radioactive Waste from Side<br />
Structural Comp<strong>on</strong>ents of a CANDU Reactor for<br />
Decommissi<strong>on</strong>ing Applicati<strong>on</strong>s in Korea<br />
Rizwan Ahmed, Gyunyoung Heo, Kyung Hee University<br />
(Korea Rep.); D<strong>on</strong>g-Keun Cho, J<strong>on</strong>gw<strong>on</strong> Choi, KAERI<br />
(Korea Rep.)<br />
4. 40068 – Uranium refining and c<strong>on</strong>versi<strong>on</strong> plant<br />
decommissi<strong>on</strong>ing project<br />
Naoki Zaima, Yasuyuki Morimoto, Noritake Sugitsue,<br />
Kazumi Kado, JAEA (Japan)<br />
—————— Break ———————<br />
5. 40161 – Radiochemical Characterizati<strong>on</strong> of C<strong>on</strong>crete<br />
Samples from the Envir<strong>on</strong>ment of Accelerator Facilities<br />
Dorothea Schumann, Paul Scherrer Institute<br />
(Switzerland)
SESSION M2: Public Involvement<br />
Wednesday 13:30 Room 303<br />
---------------------------------------------------------------------------------------<br />
Sessi<strong>on</strong> Chair: Koji Nagano, CRIEPI (Japan)<br />
1. 40288 – Activities of the OECD/NEA in the Field of<br />
Stakeholder C<strong>on</strong>fidence for Radwaste Management and<br />
Decommissi<strong>on</strong>ing<br />
Claudio Pescatore, OECD/NEA<br />
2. 40219 – A Comparative Study of Stakeholder<br />
3.<br />
Participati<strong>on</strong> in the Cleanup of Radioactive Wastes in the<br />
US, Japan and UK<br />
Mito Akiyoshi, Senshu University (Japan); William<br />
Lawless, Fjorentina Angjellari-Dajci, Paine College<br />
(USA), Christian Poppeliers, Augusta State University<br />
(USA) ; John Whitt<strong>on</strong> Nati<strong>on</strong>al Nuclear Laboratory (UK)<br />
40076 – Territorial Integrati<strong>on</strong> of the Geological<br />
Repository in France<br />
Gérald Ouzounian, Sebastien Farin, Roberto Miguez,<br />
Jean-Louis Tis<strong>on</strong>, Andra (France)<br />
4. 40256 – Public Involvement in the Closure of Fernald<br />
John Bradburne, Bradburne C<strong>on</strong>sulting LLC (USA)<br />
POSTER SESSIONS<br />
M<strong>on</strong>day PM, October 4, 2010<br />
Tuesday AM&PM, October 5, 2010<br />
SESSION L8: L/ILW Poster<br />
Room 102<br />
---------------------------------------------------------------------------------------<br />
1. 40006 – A GoldSim Modeling Approach to Safety<br />
Assessment of an LLW Repository System<br />
Youn Myoung Lee, J<strong>on</strong>gtae Je<strong>on</strong>g, J<strong>on</strong>gw<strong>on</strong> Choi,<br />
KAERI (Korea Rep.)<br />
2. 40011 – Gas Migrati<strong>on</strong> Mechanism of Saturated<br />
Highly-compacted Bent<strong>on</strong>ite and its Modeling<br />
Yukihisa Tanaka, Michihiko Hir<strong>on</strong>aga, Koji Kudo,<br />
CRIEPI (Japan)<br />
3. 40012 – Development of numerical simulati<strong>on</strong> method for<br />
gas migrati<strong>on</strong> through highly-compacted bent<strong>on</strong>ite using<br />
model of two-phase flow through deformable porous<br />
media<br />
Yukihisa Tanaka, CRIEPI (Japan)<br />
4. 40020 – Planning of Large-scale In-situ Gas Generati<strong>on</strong><br />
Experiment in Korean Radioactive Waste Repository,<br />
Juyoul Kim, Sukho<strong>on</strong> Kim, FNC Technology Co. (Korea<br />
Rep.); Jinbeak Park, Sungjoung Lee, KRMC (Korea Rep.)<br />
5. 40024 – Estimati<strong>on</strong> and measurement of porosity change<br />
in cement paste<br />
Euny<strong>on</strong>g Lee, Haeryojng Jung, Ki-jung Kw<strong>on</strong>, KRMC<br />
(Korea Rep.); Do-Gyeum Kim, Korea Institute of<br />
C<strong>on</strong>structi<strong>on</strong> Technology (Korea Rep.)<br />
6. 40082 – Separati<strong>on</strong> and Recovery of Sodium Nitrate from<br />
Low-level Radioactive Liquid Waste by Electrodialysis<br />
Yoshihiro Meguro, A Kato, Y Watanabe, Kuniaki<br />
Takahashi, JAEA (Japan)<br />
7. 40109 – Study <strong>on</strong> Mechanical Influence of Gas<br />
Generati<strong>on</strong> and Migrati<strong>on</strong> <strong>on</strong> Engineered Barrier System<br />
in adioactive Waste Disposal Facility<br />
Mamoru Kumagai, JNFL (Japan); Shuichi Yamamoto,<br />
Kunifumi Takeuchi, Obayashi Corporati<strong>on</strong> (Japan);<br />
Yukihisa Tanaka, Michihiko Hir<strong>on</strong>aga, CRIEPI (Japan)<br />
8. 40192 – Liquid Radioactive Wastes in the Republican<br />
Technical Sessi<strong>on</strong>s<br />
18<br />
Point of Burial Radioactive Waste of Tajikistan<br />
Nazirzh<strong>on</strong> Buriev, Physical-Technical Institute of the<br />
Academy of Sciences of the Republic of Tajikistan<br />
(Tajikistan)<br />
9. 40197 – Inspecti<strong>on</strong> of Burial Points of Radioactive Waste<br />
in the Republic of Tajikistan�<br />
Nazirzh<strong>on</strong> Buriev, Physical-Technical Institute of the<br />
Academy of Sciences (Tajikistan); Akram Juraev,<br />
Dzhamshed Abdushukurov, S.U.Umarov Physical<br />
Technical Institute of Academy of Sciences of Republic of<br />
Tajikistan, (Tajikistan)<br />
10. 40198 – Pre-treatment Method of Powder Waste for<br />
Vitrificati<strong>on</strong><br />
Deun-Man Kim, Hyun-Je Cho, J<strong>on</strong>g-Kil Park, Nuclear<br />
Engineering & Technology Institute (Korea Rep.)<br />
11. 40208 – Characterizati<strong>on</strong> and Pre-treatment of LLW in<br />
Turkey<br />
Ahmet Erdal Osmanlioglu, Turkish Atomic Energy<br />
Authority (Turkey)<br />
12. 40221– Dec<strong>on</strong>taminati<strong>on</strong> of Radioactive C<strong>on</strong>crete Wastes<br />
by <str<strong>on</strong>g>The</str<strong>on</strong>g>rmal and Mechanical Processes<br />
B.Y. Min, Ki W<strong>on</strong> Lee, Un Soo Chung, KAERI. W.K Choi,<br />
Kune-Woo Lee, KAERI (Korea Rep.)<br />
13. 40302 – Latex Particles Functi<strong>on</strong>alized with Transiti<strong>on</strong><br />
Metals Ferrocyanides for Cesium Uptake and<br />
Dec<strong>on</strong>taminati<strong>on</strong> of Solid Bulk Materials<br />
Dmitry Marinin, Valentin Avramenko, Dmitry Marinin,<br />
Valentin Sergienko, Institute of Chemistry FEDRAS<br />
(Russia); Veniamin Zheleznov, Irina Sheveleva, Russian<br />
Academy of Sciences (Russia)<br />
SESSION H11: SF/TRU/HLW Poster<br />
Room 102<br />
---------------------------------------------------------------------------------------<br />
1. 40001 – Investigati<strong>on</strong> of Colloid-facilitated Effects <strong>on</strong> the<br />
Radi<strong>on</strong>uclides Migrati<strong>on</strong> in the Fractured Rock with a<br />
Kinetic Solubility-Limited Dissoluti<strong>on</strong> Model<br />
Chun-Ping Jen, Nati<strong>on</strong> Chung Cheng University<br />
(Taiwan); Neng-Chuan Tien, Energy and Envir<strong>on</strong>ment<br />
Research� Laboratories, Industrial Technology Research<br />
Institute (Taiwan)<br />
2. 40013 – Modeling hydraulic c<strong>on</strong>ductivity and swelling<br />
pressure of several kinds of bent<strong>on</strong>ites affected by salinity<br />
of water<br />
Yukihisa Tanaka, Takuma Hasegawa, Kunihiko<br />
Nakamura, CRIEPI (Japan)<br />
3. 40018 – Current R & D activities of the study <strong>on</strong><br />
l<strong>on</strong>g-term stability of geological envir<strong>on</strong>ments<br />
Takahiro Hanamuro, Kenichi Yasue, Yoko<br />
Saito-Kokubu,Koichi Asamori, Tsuneari Ishimaru, Koji<br />
Umeda, JAEA (Japan)<br />
4. 40019 – In Situ Stress Measurements in Siliceous<br />
Mudst<strong>on</strong>es at Hor<strong>on</strong>obe Underground Research<br />
Laboratory, Japan<br />
Hiroyuki Sanada, Takahiro Nakamura, Yutaka Sugita,<br />
JAEA (Japan)<br />
5. 40038 – Low alkaline Cement Used in the C<strong>on</strong>structi<strong>on</strong><br />
of a Gallery in the Hor<strong>on</strong>obe Underground Research<br />
Laboratory<br />
Masashi Nakayama, Haruo Sato, Yutaka Sugita, Seiji Ito,<br />
JAEA (Japan); Masashi Minamide, Yoshito Kitagawa,<br />
Taisei Corporati<strong>on</strong> (Japan)<br />
6. 40040 – Effects of Nitrate <strong>on</strong> Nuclide Solubility for<br />
Co-locati<strong>on</strong> Disposal of TRU Waste and HLW<br />
Gento Kamei, Morihiro Mihara, JAEA (Japan);<br />
Toshiyuki Nakazawa, Norikazu Yamada, Mitsubishi
Materials Corp. (Japan)<br />
7. 40047 – A study <strong>on</strong> groundwater infiltrati<strong>on</strong> in the<br />
Hor<strong>on</strong>obe area, northern Hokkaido, Japan<br />
Hideharu Yokota, Yamamoto Yoichi, Keisuke Maekawa,<br />
Minoru Hara, JAEA (Japan)<br />
8. 40051 – Effective Use of Uranium Resources and<br />
Dissoluti<strong>on</strong> of Recovery Uranium Storage Accumulati<strong>on</strong><br />
by a Uranium Multi-recycle System<br />
Yuzo Yamashita, Yuzo Yamashita, Takeshi Nakamura,<br />
Kyushu University (Japan)<br />
9. 40053 – Advanced ORIENT Cycle - Progress <strong>on</strong> Fissi<strong>on</strong><br />
Product Separati<strong>on</strong> and Utilizati<strong>on</strong><br />
Isao Yamagishi, Masaki Ozawa, JAEA (Japan); Hitoshi<br />
Mimura, Tohoku Univ.(Japan); Shohei Kanamura, Koji<br />
Mizuguchi, Toshiba Corporati<strong>on</strong> (Japan)<br />
10. 40064 – Hydrogeological Characterizati<strong>on</strong> based <strong>on</strong> L<strong>on</strong>g<br />
Term Groundwater Pressure M<strong>on</strong>itoring<br />
Shuji Daimaru, Ryuji Takeuchi, Masaki Takeda,<br />
Masayuki Ishibashi, JAEA (Japan)<br />
11. 40065 – Development Of <str<strong>on</strong>g>The</str<strong>on</strong>g> Quality Management<br />
System For Borehole Investigati<strong>on</strong>s: (2) Quality<br />
Management Systems For Hydrochemical Investigati<strong>on</strong>s,<br />
Takanori Kunimaru, Kunio Ota, Kenji Amano, JAEA<br />
(Japan); W Russell Alexander, Bedrock Geosciences<br />
(Switzerland)<br />
12. 40067 – An Analytical Model <strong>on</strong> the Sealing Performance<br />
of Space for the Design of Buffer Material and Backfill<br />
Material<br />
Haruo Sato, JAEA (Japan)<br />
13. 40069 – Current Status of Hor<strong>on</strong>obe URL Project in<br />
C<strong>on</strong>structi<strong>on</strong> Phase<br />
Hir<strong>on</strong>obu Abe, Koichiro Hatanaka, JAEA (Japan)<br />
14. 40074 – Development of New Ultrafiltrati<strong>on</strong> Techniques<br />
Maintaining In-Situ Hydrochemical C<strong>on</strong>diti<strong>on</strong>s for<br />
Colloidal Study<br />
Daisuke Aosai, Yuhei Yamamoto, Takashi Mizuno, JAEA<br />
(Japan)<br />
15. 40089 – Sorpti<strong>on</strong> Behavior of Iodine <strong>on</strong> Calcium Silicate<br />
Hydrates Formed as a Sec<strong>on</strong>dary Mineral<br />
Keisuke Shirai, Yuichi Niibori, Akira Kirishima, Hitoshi<br />
Mimura, Tohoku Univ. (Japan)<br />
16. 40098 – Development of the Quality Management System<br />
for Borehole Investigati<strong>on</strong>s: (1) Quality Management<br />
System for Hydraulic Packer Tests<br />
Shinji Takeuchi, Takanori Kunimaru, Kunio Ota, JAEA<br />
(Japan); Bernd Frieg, Nagra (Switzzerland)<br />
17. 40101 – Comparis<strong>on</strong> of Post-Irradiati<strong>on</strong> Experimental<br />
Data and <str<strong>on</strong>g>The</str<strong>on</strong>g>oretical Calculati<strong>on</strong>s for Inventory<br />
Estimati<strong>on</strong> of L<strong>on</strong>g-Lived fissi<strong>on</strong> Products in Spent<br />
Nuclear Fuel<br />
Shiho Asai ,Yukiko Hanzawa, Keisuke Okumura, Hideya<br />
Suzuki, Masaaki Toshimitsu, Nobuo Shinohara, JAEA<br />
(Japan); Kensuke Suzuki, Satoru Kaneko, Tokyo Electric<br />
Power Company (Japan)<br />
18. 40103 – Selective Uptake of Palladium from High-Level<br />
Liquid Wastes by Hybrid Microcapsules<br />
Hitoshi Mimura, Takashi Sakakibara, Yan Wu, Yuichi<br />
Niibori, Tohoku Univ. (Japan); Shin-ichi Koyama,<br />
Takashi Ohnishi, JAEA (Japan)<br />
19. 40113 – An Empirical Model To Determine <str<strong>on</strong>g>The</str<strong>on</strong>g> Modes<br />
Of Corrosi<strong>on</strong> Of Carb<strong>on</strong> Steel<br />
Toshikatsu Maeda, Masatoshi Watanabe, Seiji Takeda,<br />
Shinichi Nakayama, JAEA (Japan)<br />
20. 40124 – Trends in Scenario Development Methodologies<br />
and Integrati<strong>on</strong> in NUMO's Approach<br />
Takeshi Ebashi, Katsuhiko Ishiguro, NUMO (Japan);<br />
Keiichiro Wakasugi, JAEA (Japan); Hideki Kawamura,<br />
Technical Sessi<strong>on</strong>s<br />
19<br />
Obayashi Corporati<strong>on</strong> (Japan); Irina Gaus, Stratis<br />
Vomvoris, Andrew Martin, Nagra (Switzerland); Paul<br />
Smith, Safety Assessment Management (UK)<br />
21. 40137 – Development of Methodology to C<strong>on</strong>struct a<br />
Generic C<strong>on</strong>ceptual Model of River-valley Evoluti<strong>on</strong> for<br />
Performance Assessment of HLW Geological Disposal<br />
Makoto Kawamura, Kenichi Yasue, Tadafumi Niizato,<br />
Shin-ichi Tanikawa, JAEA (Japan)<br />
22. 40162 – L<strong>on</strong>g-term Stability of Bent<strong>on</strong>ite Material Used<br />
as Engineered Barrier for Radioactive Waste Disposal ,<br />
Vera Jedinakova-Krizova, Katerina Videnska, Institute of<br />
Chemical Chechnology Prague (Czech Republic); Eduard<br />
Hanslik, T.G.M. Water Research Institute (Czech<br />
Republic)<br />
23. 40173 – Development of a methodology for evaluating<br />
the performance of host rock for geological disposal<br />
based <strong>on</strong> surface-based investigati<strong>on</strong>s<br />
Manabu Inagaki, Keisuke Maekawa, JAEA (Japan);<br />
Tatsuya Tanaka, Shuji Hashimoto, Obayashi Corporati<strong>on</strong><br />
(Japan)<br />
24. 40176 – Structural Integrity Evaluati<strong>on</strong> Approach for<br />
PWR Spent Nuclear Fuel<br />
Yun Seog Nam, Se<strong>on</strong>g Ki Lee, Y<strong>on</strong>g Hwan Kim, Je<strong>on</strong><br />
Kye<strong>on</strong>g Lak, Choi Ki Sung, Chang Sok Cho, KNF (Korea<br />
Rep.)<br />
25. 40200 – Development of Program Categories to Assess<br />
the Radiological Dosage during Spent Fuel Transportati<strong>on</strong><br />
Suh<strong>on</strong>g Lee, Sangw<strong>on</strong> Shin, Enesys, Jaemin Lee,<br />
Enesys.Co., Ltd. (Korea Rep.); Kiyroul Se<strong>on</strong>g,<br />
Je<strong>on</strong>ghyoun Yo<strong>on</strong>, KRMC (Korea Rep.)<br />
26. 40225 – Exploiting synergies between the UK & Japanese<br />
geological disposal programmes�<br />
Ellie Scourse, Atkins (UK); Hideki Kawamura, Obayashi<br />
Corporati<strong>on</strong> (Japan); Ian G. McKinley, McKinley<br />
C<strong>on</strong>sulting (Switzerland)<br />
27. 40239 – Realistic C<strong>on</strong>sequence Analysis of River Erosi<strong>on</strong><br />
Scenarios for a HLW epository�<br />
Kaname Miyahara, Makoto Kawamura, Manabu Inagaki,<br />
JAEA (Japan); Ian G. McKinley, McKinley C<strong>on</strong>sulting<br />
(Switzerland); Michael J. Apted, M<strong>on</strong>itor Scientific LLC<br />
(USA)<br />
28. 40272 – Removal of Fissi<strong>on</strong> Products in the Spent<br />
Electrolyte Using Ir<strong>on</strong> Phosphate Glass as a Sorbent<br />
Ippei Amamoto, Masami Nakada, Yoshihiro Okamoto,<br />
JAEA (Japan); Naoki Mitamura, Tatsuya Tsuzuki, Central<br />
Glass Co., Ltd. (Japan); Yasushi Takasaki, Atsushi<br />
Shibayama, Akita University (Japan); Tetsuji Yano, Tokyo<br />
Institute of Technology (Japan)<br />
29. 40295 – Propagati<strong>on</strong> and Interacti<strong>on</strong>s of Acoustic Waves<br />
in a Waveguide Attached at the Surface of Rock<br />
Jin-Seop Kim, Kyung-Soo Lee, S. Kw<strong>on</strong>, KAERI (Korea<br />
Rep.); Gye-Chun Cho, KAIST (Korea Rep.)<br />
SESSION D7: D&D Poster<br />
Room 102<br />
---------------------------------------------------------------------------------------<br />
1. 40009 – Decommissi<strong>on</strong>ing of the KRR-1 & 2 Research<br />
Reactors at KAERI; Summary <strong>on</strong> the Project<br />
Jin Ho Park, KAERI (Korea Rep.)<br />
2. 40075 – Methods of Selected Input Calculati<strong>on</strong> Data<br />
Verificati<strong>on</strong> And <str<strong>on</strong>g>The</str<strong>on</strong>g>ir Influence On Decommissi<strong>on</strong>ing<br />
Cost In the OMEGA Code<br />
Frantisek Ondra. Vladimir Daniska, Ivan Rehak, Oto<br />
Schultz, DECONTA, a.s. (Slovakia); Vladimir Necas,<br />
Slovak University of Technology in Bratislava (Slovakia)<br />
3. 40078 – Experience of MR and RFT Reactors’
Decommissi<strong>on</strong>ing in RRC “Kurchatov Institute”<br />
Alexander V. Chesnokov, Victor Volkov, Sergey<br />
Semenov, Vitaly Pavlenko, Vyacheslav Kolyadin, D.<br />
Muzrukova, RRC "Kurchatov Institute" (Russia); Artur<br />
Arustamov, SUE SIA "Rad<strong>on</strong>" (Russia)<br />
4. 40126 – Detailed Standardized Decommissi<strong>on</strong>ing<br />
Parameters Calculati<strong>on</strong> for Larger echnological<br />
Aggregates and Relevant Buildings in Nuclear Power<br />
Plants using the OMEGA Code<br />
Peter Bezak, Vladimir Daniska, DECONTA, a.s.<br />
(Slovakia); Ivan Rehak, DECOM, a.s . (Slovakia)<br />
5. 40190 – Dismantling Method of Fuel Cycle Facilities<br />
Obtained by Dismantling of the JRTF<br />
Fumihiko Kanayama, JAEA (Japan)<br />
6. 40191 – Computer Simulati<strong>on</strong> of Cryogenic Jet Cutting<br />
for Dismantling Highly Activated Facilities<br />
Sung-Kyun Kim, Kune-Woo Lee, KAERI (Korea Rep.)<br />
7. 40193 – Strippable Core-shell Polymer Emulsi<strong>on</strong> for<br />
Dec<strong>on</strong>taminati<strong>on</strong> of Radioactive Surface C<strong>on</strong>taminati<strong>on</strong><br />
Bum-Kyoung Seo, Bum-Kyoung Seo, Kune-Woo Lee,<br />
KAERI (Korea Rep.)<br />
SESSION R4: ER Poster<br />
Room 102<br />
---------------------------------------------------------------------------------------<br />
1. 40025 – Improvement of quicklime mixing treatment by<br />
carb<strong>on</strong> dioxide ventilati<strong>on</strong><br />
Yuki Nakagawa, Hisayoshi Hashimoto, Hitachi<br />
C<strong>on</strong>structi<strong>on</strong> Machinery Co., Ltd. (Japan); Koichi Suto,<br />
Chihiro Inoue, Tohoku University (Japan)<br />
2. 40166 – Procedure and result of decommissi<strong>on</strong> of R&D<br />
facility of Uranium fuel<br />
Hirokazu Tanaka, Masao Shimizu, Ryoji Tanimoto,<br />
Kazuhiko Maekawa, Shinzo Ueta, Mitsubishi Materials<br />
Corporati<strong>on</strong> (Japan); Susumu Tojo, SERNUC<br />
Corporati<strong>on</strong> (Japan)<br />
3. 40210 – Photo-Catalytic Degradati<strong>on</strong> of Industrial<br />
Pollutant by Using Nano-technology and Solar energy in<br />
the Eastern Area of Kingdom of Saudi Arabia<br />
Osama S.Y. Mohamed, Abdullah A. Al Jaafari, King<br />
Faisal University (Saudi Arabia)<br />
4. 40224 – Hydrogen Producti<strong>on</strong> from a PV/PEM<br />
Electrolyzer System Using a Neural-Network-Based<br />
MPPT Algorithm<br />
Abd El-Shafy Nafeh, Electr<strong>on</strong>ics Research Institute<br />
(Egypt)<br />
5. 40301 – Cement based solidificati<strong>on</strong> / stabilizati<strong>on</strong> of<br />
industrial c<strong>on</strong>taminated soil using various cement<br />
additives<br />
Grega E. Voglar, RDA (Slovenia); D. Lestan,<br />
Agr<strong>on</strong>omy Department, Biotechnical Faculty, University<br />
of Ljubljana, (Slovenia)<br />
SESSION M3: EM/PI Poster<br />
Room 102<br />
---------------------------------------------------------------------------------------<br />
1. 40099 – Removal of Fluorine and Bor<strong>on</strong> from<br />
Groundwater Using Radiati<strong>on</strong>-induced Graft<br />
Polymerizati<strong>on</strong> Adsorbent at Mizunami Underground<br />
Research Laboratory<br />
Yosuke Iyatomi, Hiroyuki Hoshina, Noriaki Seko, Noboru<br />
Kasai, Yuji Ueki, Masao Tamada, JAEA (Japan)<br />
2. 40184 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Optimized Risk Management of the Waste<br />
from NORM and Nuclear Industries - How to Harm<strong>on</strong>ize<br />
Technical Sessi<strong>on</strong>s<br />
20<br />
Risk from Various Sources<br />
Yoko Fujikawa, Kyoto University Research Reactor<br />
Institute (Japan); Michikuni Shimo, Fujita Health<br />
University (Japan); Hidenori Y<strong>on</strong>ehara, Nati<strong>on</strong>al<br />
Instuitute of Radiological Sciences (Japan); Tadashi<br />
Tujimoto, Electr<strong>on</strong> Science Institute (Japan)<br />
3. 40205 – Exposure Dose Evaluati<strong>on</strong> of Worker at<br />
Radioactive Waste Incinerati<strong>on</strong> Facility <strong>on</strong> KEARI<br />
Sang Kyu Park, J<strong>on</strong>g Se<strong>on</strong> Je<strong>on</strong>, Younhwa Kim, Jaemin<br />
Lee, NESYS.CO., LTD (Korea Rep.); Ki W<strong>on</strong> Lee, KAERI,<br />
(Korea Rep.)<br />
4. 40209 – Scenario Development for Safety Assessment of<br />
Waste Repository for Feasibility Study <strong>on</strong> Transmutati<strong>on</strong><br />
of Spent Nuclear Fuel into LILW using PEACER<br />
Sung-yeop Kim, Kun Jai Lee, KAIST (Korea Rep.)
List of Exhibitors<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> following exhibitors are greatly appreciated:<br />
(Exhibitors in Alphabetical Order)<br />
�� Belgoprocess<br />
�� Central Research Institute of Electric Power Industry<br />
�� Fuji Electric Systems Co., Ltd.<br />
�� GEOSCIENCE RESEARCH LABORATORY Co., Ltd.<br />
�� JAPAN NUCLEAR FUEL LIMITED<br />
�� Kajima Corporati<strong>on</strong><br />
�� Kobe Steel, Ltd. (KOBELCO)<br />
�� Mitsubishi Materials Corporati<strong>on</strong><br />
�� NIPPON KOEI Co., Ltd.<br />
�� Nuclear Waste Management Organizati<strong>on</strong> of Japan (NUMO)<br />
�� OBAYASHI CORPORATION<br />
�� PIERCAN USA, Inc.<br />
�� Raax Co., Ltd. / Earth Scanning Associati<strong>on</strong><br />
�� SHIMIZU CORPORATION<br />
�� TAISEI CORPORATION<br />
�� Toshiba Corporati<strong>on</strong><br />
�� Web I Laboratories, Inc.<br />
�� Westinghouse Electric Company<br />
21
Nuclear Power Generati<strong>on</strong> /<br />
Nuclear Fuel Cycle Related Facilities<br />
1<br />
Fuji�s 3 unique technologies which include remote handling, radwaste<br />
treatment and high temperature gas-cooled reactor are c<strong>on</strong>tributing for<br />
ensuring energy resources for l<strong>on</strong>ger than a century.<br />
Remote Handling & Fuel Fabricati<strong>on</strong> Technologies<br />
Fuel Pellets Manufacturing Facility Internal Equipment within the Glove Box<br />
Performance of<br />
volume reducti<strong>on</strong><br />
(i<strong>on</strong>-exchange resin)<br />
(1/10–1/20)<br />
Exterior View of Fuji Resin Reducer(LPOP)<br />
(LPOP : Low Pressure Oxidati<strong>on</strong> Process)<br />
Commercial High<br />
Temperature Gascooled<br />
Reactor<br />
(HTGR)<br />
Active Core<br />
(Fuel Blocks)<br />
Core Bottom<br />
Structure<br />
pellet<br />
inspecti<strong>on</strong><br />
(<str<strong>on</strong>g>The</str<strong>on</strong>g> HTGR heat utilizati<strong>on</strong> plant)<br />
C<strong>on</strong>tact : Fuji Electric Corp. of America<br />
Ph<strong>on</strong>e 201-712-0555 FAX 201-368-8258<br />
URL http//www.fujielectric.com/fecoa /<br />
Gripper<br />
: Fuji Electric Systems Co., Ltd.<br />
Ph<strong>on</strong>e +81-44-329-2169 FAX +81-44-329-2178<br />
URL http://www.fujielectric.com/<br />
����������� ����������������������������������������������������������<br />
Fuel Transfer System<br />
2 Radwaste Treatment Systems & Decommissi<strong>on</strong>ing Technologies<br />
Cutting Torch<br />
Reactor Vessel<br />
Verificati<strong>on</strong> test of remote dismantling system<br />
(Tokai-1 Decommissi<strong>on</strong>ing)<br />
3 Reactor Technology for High Temperature Gas-cooled Reactor<br />
24<br />
HTTR Core internals<br />
Top view of the core<br />
(Outer diameter 4.25m)<br />
(HTTR : High Temperature Engineering Test Reactor)
Abstracts<br />
OPENING SESSION<br />
“Nuclear Energy Strategy for Sustainable Growth:<br />
Aiming at Green Innovati<strong>on</strong> and Life Innovati<strong>on</strong>”<br />
Tatsujiro Suzuki, Vice Chairman, Japan Atomic Energy Commissi<strong>on</strong> (Japan)<br />
Japan Atomic Energy Commissi<strong>on</strong> released a report, entitled “Nuclear Energy Strategy for Growth” <strong>on</strong> May 25,<br />
2010. <str<strong>on</strong>g>The</str<strong>on</strong>g> report is intended to c<strong>on</strong>tribute the government’s “New Growth Strategy” which was eventually released in<br />
June 18, 2010. This JAEC’s report emphasizes the role of nuclear energy technologies for “green innovati<strong>on</strong>” and “life<br />
innovati<strong>on</strong>” which are two primary comp<strong>on</strong>ents of New Growth Strategy. <str<strong>on</strong>g>The</str<strong>on</strong>g> key messages included in the report are<br />
“strengthening capability to meet global challenges” and “enhancing citizen’s c<strong>on</strong>fidence in nuclear energy<br />
technologies”.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> report listed five major recommendati<strong>on</strong>s as follows.<br />
1. Improve performance of nuclear power plants aim<br />
2. ing at the world best class and take necessary measures for adding more nuclear plants to achieve<br />
increased share of nuclear power in total power generati<strong>on</strong> for “green innovati<strong>on</strong>” Promote industrial<br />
applicati<strong>on</strong> of radiati<strong>on</strong> technologies, such as medial, agricultural and scientific applicati<strong>on</strong>s, as<br />
“strategic industry” for life innovati<strong>on</strong><br />
3. Develop social and ec<strong>on</strong>omic envir<strong>on</strong>ments for achieving above goals, which include; (1) improve<br />
scientific literacy (2) take new initiatives for data/informati<strong>on</strong> disclosure (3) enhance ec<strong>on</strong>omic<br />
visualizati<strong>on</strong> of CO2 merits of nuclear energy (4) reform safety regulatory structure to improve<br />
public c<strong>on</strong>fidence (5) develop better approaches for improving local community development and<br />
nuclear related facilities (6) develop public/private human network in Asia.<br />
4. Develop appropriate measures to meet increasing global needs for nuclear power and radiati<strong>on</strong><br />
technologies<br />
5. Develop l<strong>on</strong>g term social platform for sustainable growth for nuclear energy technologies.<br />
“U.S. Office of Envir<strong>on</strong>mental Management - World Leaders in Nuclear Cleanup and C<strong>on</strong>structi<strong>on</strong>”<br />
Dae Y. Chung, Principal Deputy Assistant Secretary for Envir<strong>on</strong>mental Management, US DOE (USA)<br />
U.S. Department of Energy Principal Deputy Assistant Secretary for Envir<strong>on</strong>mental Management, Dae Chung, will<br />
present an overview of the progress, challenges, and future opportunities associated with the world's largest nuclear<br />
cleanup program. <str<strong>on</strong>g>The</str<strong>on</strong>g> Office of Envir<strong>on</strong>mental Management (EM) is resp<strong>on</strong>sible for the safe cleanup of over two<br />
milli<strong>on</strong> acres of land located in 34 states. EM employs more than 30,000 people – primarily scientists, engineers, and<br />
hazardous waste technicians, and has an annual budget of approximately $6 billi<strong>on</strong>.<br />
“Recent Progress in Radioactive Waste Management in Korea”<br />
Ho Taek Yo<strong>on</strong>, Senior Vice President, KRMC (Korea Rep.)<br />
Republic of Korea is set to become a major nuclear power generati<strong>on</strong> country. Nuclear energy initiative is a<br />
strategic priority for R.O.K, and of which nuclear share in electricity generati<strong>on</strong> is planned to become 56% by 2030, with<br />
nuclear installed capacity of 35 GWe. Currently, 20 reactors with installed capacity of 17.7 GWe provide almost 40% of<br />
domestic electricity demand. However, the very active nuclear power program inevitably causes increase in the build-up<br />
of the radioactive wastes including Low- and Intermediate-Level radioactive Waste (LILW) and spent nuclear fuel.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>refore, reliable and effective management of the radioactive waste and spent nuclear fuel has become a key agenda<br />
for the c<strong>on</strong>tinuous growth of the nuclear power program.<br />
LILW generated by the nuclear power plants is being tentatively stored at each reactor site. <str<strong>on</strong>g>The</str<strong>on</strong>g> accumulated<br />
amount of LILW in Korea’s nuclear power plants as of Dec. 2009 is approximately 87,000 drums (200 liter drum). And<br />
together with those of research institutes, nuclear fuel manufacturer, general industry and medical sectors reached<br />
approximately 112,000 drums (200 liter drum). <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>structi<strong>on</strong> of a final repository is urgently needed to manage the<br />
radioactive waste effectively and safely.<br />
Efforts to secure site for the radioactive waste disposal facility in Korea began in 1986. In 18 years from 1986 to<br />
2004, nine attempts of site selecti<strong>on</strong> had been executed unfruitfully. In the 10th attempt which was made in 2005, Korean<br />
government requested that the public acceptance shall be c<strong>on</strong>firmed through resident voting at the each local government<br />
volunteering for the repository hosting and decided that the spent nuclear fuel site will be separated from LILW disposal<br />
site, and the community support packages will be guaranteed by the law. Under the above menti<strong>on</strong>ed basic principles, the<br />
resident vote was implemented in the four volunteered local governments including Gunsan-kun, Youngdok-kun, Pohang<br />
city, and Gye<strong>on</strong>gju city. Am<strong>on</strong>g these local governments, Gye<strong>on</strong>gju city recorded the highest c<strong>on</strong>sent vote rate (89.5%)<br />
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and became the hosting city of LILW repository site.<br />
After the vote, <strong>on</strong> January 2, 2006, the Ministry of Knowledge and Ec<strong>on</strong>omy (MKE) designated B<strong>on</strong>ggil-ri,<br />
Yangbuk-mye<strong>on</strong>, Gye<strong>on</strong>gju-city, North Gye<strong>on</strong>gsang Province (approximately 2,100,000 m2) as the LILW repository site.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> first stage Wols<strong>on</strong>g disposal facility c<strong>on</strong>structi<strong>on</strong> will be completed by December 2012 as underground silos type<br />
with a disposal capacity of 100,000 drums.<br />
Spent nuclear fuels generated from nuclear power plants are stored at reactor sites pending c<strong>on</strong>structi<strong>on</strong> of an<br />
interim storage facility or final repository. <str<strong>on</strong>g>The</str<strong>on</strong>g> cumulative amount of spent fuel is about 10,761 t<strong>on</strong>s as of Dec. 2009, and<br />
is expected to increase up to 20,000 t<strong>on</strong>s by 2020. <str<strong>on</strong>g>The</str<strong>on</strong>g> existing storage capacity as of Dec. 2009 is 13,532 t<strong>on</strong>s.<br />
Nati<strong>on</strong>al policy for spent nuclear fuel management shall be decided in a timely manner through public participati<strong>on</strong><br />
process taking into c<strong>on</strong>siderati<strong>on</strong> of current internati<strong>on</strong>al trends and technology development. KRMC launched the spent<br />
fuel management alternative study and establishment of road map in Dec. 2009 to promote expert group’s c<strong>on</strong>sensus and<br />
for the public involvement in the future which is approaching imminently.<br />
“Radioactive waste management – achievements, needs and future expectati<strong>on</strong>s”<br />
Irena Mele, Head of Waste Technology Secti<strong>on</strong>, Divisi<strong>on</strong> of Nuclear Fuel Cycle and Waste Technology, IAEA<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> nuclear community is facing a period of dynamic changes. <str<strong>on</strong>g>The</str<strong>on</strong>g> growing interest for nuclear energy<br />
brings new optimism to the community but also new challenges and increased resp<strong>on</strong>sibilities. Radioactive waste<br />
management remains <strong>on</strong> the agenda even in most developed nuclear countries. Although significant progress has been<br />
achieved in this area and many disposal soluti<strong>on</strong>s for different types of waste have been successfully implemented<br />
worldwide, unresolved disposal of HLW and spent nuclear fuel remains the major c<strong>on</strong>cern of the public related to the use<br />
of nuclear energy and may become an obstacle for the planned expansi<strong>on</strong> of their nuclear programmes. <str<strong>on</strong>g>The</str<strong>on</strong>g>re are also<br />
countries that are still missing necessary radioactive waste management infrastructure and, thus, capacity and capability<br />
to safely manage their low level and intermediate level radioactive waste. In spite of well developed and available waste<br />
management technologies and good practices many our Members States are still meeting great deficiency in radioactive<br />
waste management infrastructure and need str<strong>on</strong>g support and assistance to develop adequate level for safe and efficient<br />
management of their radioactive waste. In particular countries with <strong>on</strong>ly instituti<strong>on</strong>al waste experience great difficulties<br />
in providing waste management facilities due to the lack of capacity and expertise.<br />
Many new countries have also expressed their interest and intenti<strong>on</strong> to embark <strong>on</strong> nuclear energy. When planning<br />
and preparing for new nuclear build, major attenti<strong>on</strong> is given to the c<strong>on</strong>structi<strong>on</strong> and operati<strong>on</strong> of nuclear power plant and<br />
infrastructure building. Much less attenti<strong>on</strong> of those countries and also nuclear industry is given to the fact that in parallel<br />
with the NPP the radioactive waste management infrastructure needs to be developed as well. A big challenge is to<br />
increase awareness am<strong>on</strong>g those countries and also am<strong>on</strong>g nuclear industry <strong>on</strong> burning need to include also preparati<strong>on</strong>s<br />
for spent fuel and radioactive waste management in early planning process.<br />
Decommissi<strong>on</strong>ing of nuclear facilities has become a mature technology and planning for decommissi<strong>on</strong>ing and<br />
implementing a decommissi<strong>on</strong>ing plan is comm<strong>on</strong>ly accepted practice in most of nuclear countries. However, additi<strong>on</strong>al<br />
encouragement and support is still needed in countries with less experience and smaller programmes. Another<br />
important issue is cleaning-up of sites with legacy waste emanating from past research, medical or military activities.<br />
Important legacies from earlier uranium mining are known in many parts of the world. Remediati<strong>on</strong> of land c<strong>on</strong>taminated<br />
by radioactive material residues is needed in many countries, like in the Central Asian republics, where the remedial<br />
challenges will require a c<strong>on</strong>solidated internati<strong>on</strong>al support approach.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper will provide an overview of current situati<strong>on</strong> and future prospects in all these areas of radioactive waste<br />
management, decommissi<strong>on</strong>ing and envir<strong>on</strong>mental remediati<strong>on</strong> and highlight the role and efforts of the IAEA to ensure<br />
that adequate safety standards in this area are applied worldwide, that experiences and good practices gained in<br />
radioactive waste management area are shared and communicated between the countries and potential users, and that<br />
proper assistance is provided to countries c<strong>on</strong>sidering nuclear power.<br />
SESSION L1: Waste Management<br />
1) 40081 – Radioactive Waste: Feedback of 40-year Operati<strong>on</strong>s in France<br />
Michel Dutzer, Gérald Ouzounian, Roberto Miguez, Jean-Louis Tis<strong>on</strong>, Andra (France)<br />
France's experience in the management of radioactive waste is supported by forty years of operati<strong>on</strong>al activities in<br />
the field of surface disposal. This feedback is related to three disposal facilities:<br />
- Centre de la Manche disposal, not far away Cherbourg, from design to post-closure facility,<br />
- Centre at Soulaines-Dhuys from site selecti<strong>on</strong> to design to operati<strong>on</strong> during nearly 20 years,<br />
- Centre at Morvilliers from site selecti<strong>on</strong> to operati<strong>on</strong> for seven years now.<br />
During the operati<strong>on</strong>al period of Centre de la Manche disposal facility (1969-1994), the safety c<strong>on</strong>cept for low-and<br />
intermediate level short lived waste (LIL-SLW) was developed and progressively incorporated in the procedures of the<br />
facility. <str<strong>on</strong>g>The</str<strong>on</strong>g> facility entered its instituti<strong>on</strong>al c<strong>on</strong>trol period and the experience of this facility has been useful for the<br />
operating facilities.<br />
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Centre de l’Aube that took over Centre de la Manche, and Morvilliers for very low level wastes. Both facilities<br />
currently accommodate the major part of the volume of radioactive wastes that are generated in France. However<br />
disposal facilities have to be c<strong>on</strong>sidered as rare resources. <str<strong>on</strong>g>The</str<strong>on</strong>g>n new waste management opti<strong>on</strong>s are being investigated as<br />
the disposal of large comp<strong>on</strong>ents or recycling metallic wastes within the nuclear industry.<br />
2) 40227 – ILW Characterisati<strong>on</strong> and Strategy Development at Chapelcross Power Stati<strong>on</strong>, Dumfriesshire,<br />
Scotland<br />
Rob Hodgs<strong>on</strong>, Alastair Stewart, Greg Wotherspo<strong>on</strong>, Magnox North (UK);<br />
Vince Cane, Dr Rob Thied, Nuclear Technologies PLC (UK)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> decommissi<strong>on</strong>ing strategy team at Chapelcross is c<strong>on</strong>ducting work to establish a robust and compliant strategy<br />
for the discharge of its intermediate level waste (ILW) liabilities.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> work is supported by staff from the Envir<strong>on</strong>ment and Radioactive Waste Management Team at Nuclear<br />
Technologies PLC. A circa. £1.2M ($1.85M) 32 m<strong>on</strong>th c<strong>on</strong>tract was placed in 2008 for the development of a fully<br />
developed strategy and outline c<strong>on</strong>cept design, supported by an integrated programme of waste characterisati<strong>on</strong> tasks.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> characterisati<strong>on</strong> programme was designed to improve understanding of the relevant waste streams and to<br />
underpin future design development by removing risk and uncertainty at the outset of the project.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> characterisati<strong>on</strong> work involved;<br />
• Desktop studies<br />
• Trace element analysis and activati<strong>on</strong> calculati<strong>on</strong>s,<br />
• In-situ underwater radiometric surveys<br />
• P<strong>on</strong>d sludge sampling and analysis<br />
• P<strong>on</strong>d Zeolite skip sampling and analysis<br />
• Reactor humidrier desiccant sampling and analysis<br />
In what is believed to represent a worldwide first, in applicati<strong>on</strong> to intermediate level waste , the project team<br />
utilised the US EPA’s ‘Data Quality Objectives’ methodology (DQO) to ensure a right first time approach to the delivery<br />
of the characterisati<strong>on</strong> work. <str<strong>on</strong>g>The</str<strong>on</strong>g> DQO approach has been designed to ensure that, prior to c<strong>on</strong>ducting R&D tasks, the<br />
specificati<strong>on</strong> of the task is robustly c<strong>on</strong>sidered and a comprehensive plan put in place. This approach aligns well with<br />
project management best practice. DQO will also ensure that specificati<strong>on</strong>s for analysis of samples are based up<strong>on</strong> a clear<br />
understanding of the future use of the data.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> work was supported by a number of specialist sub-c<strong>on</strong>tractors and the entire task managed under the auspices<br />
of an integrated project team, with stakeholders from all parties<br />
involved in the key elements of decisi<strong>on</strong> making. DQO workshops were run to achieve this c<strong>on</strong>sensus approach and<br />
as a result a successful delivery programme has been implemented.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper to be presented will focus <strong>on</strong> the applicati<strong>on</strong> of DQO and will dem<strong>on</strong>strate how the process was used to<br />
design the various R&D programmes.<br />
Sec<strong>on</strong>dary benefits of the process include a fully transparent audit trail which will allow future analysis of the<br />
project to track key decisi<strong>on</strong> points, and a comprehensive quality/knowledge management system with literally thousands<br />
of quality records tracing every step of the R&D tasks from incepti<strong>on</strong> through to delivery of final reports, thereby<br />
enabling full c<strong>on</strong>siderati<strong>on</strong> of results in future design decisi<strong>on</strong>s.<br />
3) 40226 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Ethics of the Management of Low and Intermediate Radioactive Wastes Generated by<br />
Cernavoda NPP, a Challenge for the Romanian Specialists<br />
Gheorghe Barariu, Subsidiary of Technology and Engineering for Nuclear Objectives (Romania)<br />
In Romania there was an extensive interest <strong>on</strong> treatment of radioactive wastes generated by nuclear technology used<br />
in industrial and research field. Still the existence of NPP Cernavoda and the provisi<strong>on</strong> for a new nuclear power plant<br />
impose the existence of the disposal capacities for future radioactive wastes that will be further generated by operati<strong>on</strong><br />
and decommissi<strong>on</strong>ing of new units. <str<strong>on</strong>g>The</str<strong>on</strong>g> key aspects of the radioactive wastes management at the Romanian Cernavoda<br />
NPP equipped with CANDU 600 reactors result from missing of a Radioactive Waste Treatment Plant. <str<strong>on</strong>g>The</str<strong>on</strong>g> Strategy for<br />
radioactive waste management was elaborated by the former Nati<strong>on</strong>al Agency for Radioactive Waste (ANDRAD), the<br />
jurisdicti<strong>on</strong>al authority for final disposal and the coordinati<strong>on</strong> of nuclear spent fuel and radioactive waste management<br />
(Order 844/2004), with attributi<strong>on</strong>s established by Governmental Decisi<strong>on</strong> (GO) 31/2006. <str<strong>on</strong>g>The</str<strong>on</strong>g> Strategy specifies the<br />
commissi<strong>on</strong>ing of the Saligny L/IL Radwaste Repository near Cernavoda NPP, in 2014. <str<strong>on</strong>g>The</str<strong>on</strong>g> new Agency AN&DR,<br />
Nuclear Agency and for Radioactive Waste which was appointed in 2010, probable will follows the same Strategy. A lot<br />
of c<strong>on</strong>straints, including limited available surface and bearing capacity <strong>on</strong> site of the Saligny Repository near Cernavoda<br />
NPP limits the possibilities for selecting of the technologies for radioactive wastes treatment. For the new NPP not sised<br />
and located yet wil be provided a separate strategy. Based <strong>on</strong> the input data the main c<strong>on</strong>straints for the new repository<br />
design were identified: Cernavoda NPP specific waste characterizati<strong>on</strong> is not finalized, the wastes are not properly<br />
c<strong>on</strong>diti<strong>on</strong>ed for the final disposal, envir<strong>on</strong>mental c<strong>on</strong>straints due to characteristics of the Saligny Repository, regulatory<br />
c<strong>on</strong>straints, public acceptance c<strong>on</strong>straints, c<strong>on</strong>straints related Utility c<strong>on</strong>cept for treatment of radioactive waste,<br />
uncertenties related the New Governamental Agency AN&DR. For every c<strong>on</strong>straint menti<strong>on</strong>ed above, suitable measures<br />
will be taken to reduce the uncertainties. <str<strong>on</strong>g>The</str<strong>on</strong>g> most important technological dilema is related to selecti<strong>on</strong> betwen<br />
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Abstracts<br />
technogies that implies impact <strong>on</strong> present generati<strong>on</strong> ( incinerati<strong>on</strong>, radwaste transfer from ss drums to cs drums and ss<br />
drums supercompacti<strong>on</strong> ), and technologies that c<strong>on</strong>fined the tritium and C-14 in the Repository with impact for next<br />
generati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper will present the implicative of this selecti<strong>on</strong> <strong>on</strong> the future Radioactive Waste Treatment Plant.<br />
4) 40149 – CEA's radioactive waste and unused fuel inventory - Marcoule site example<br />
Jean-Guy Nokhamz<strong>on</strong>, Marc Butez, Ddaniel Fulleringer, CEA (France)<br />
In the field of clean up and decommissi<strong>on</strong>ing of nuclear facilities the knowledge of the radioactive waste and<br />
unused fuel inventories is crucial. For CEA (French Commissi<strong>on</strong> in charge of Atomic Energy and Alternative Energies),<br />
this knowledge is a key issue : in the short term for the flows stream lining as well as in the middle and l<strong>on</strong>g terms for<br />
investment strategy in nuclear support facilities.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se needs appear in a larger extent at the nati<strong>on</strong>al scale in France, with the enforcement of two laws promulgated<br />
in 2006 dealing with radioactive waste and with transparency in Nuclear Safety.<br />
More generally, a precise and reliable knowledge of inventory and flow producti<strong>on</strong> forecast is indispensable to give<br />
pertinent answers to the questi<strong>on</strong>s related to waste valuati<strong>on</strong>. Thus, all these subjects are also worked out with our<br />
authorities in charge of financial aspects because there are essential for the cost c<strong>on</strong>trol of clean-up and decommissi<strong>on</strong>ing<br />
projects CEA has to manage. In effect, in these projects, waste management represents a great part of cost and risk.<br />
For all these reas<strong>on</strong>s CEA has carried out an important work to collect all his waste and unsued fuel inventories. For<br />
this reas<strong>on</strong> we have developed a new "INFLUVAL" data base which will be combined with a softare featured with<br />
coherency checking and analysis modules. Indeed, we must guarantee uniqueness and relevance of data coming from<br />
decommissi<strong>on</strong>ing projects and facility managers.<br />
As a c<strong>on</strong>sequence, in 2009 CEA Clean-up and Decommissi<strong>on</strong>ing Divisi<strong>on</strong> has decided to perform, , a<br />
comprehensive inventory of waste and unused fuel with the following objectives :<br />
- C<strong>on</strong>solidati<strong>on</strong> of stock and expected flows,<br />
- Evaluati<strong>on</strong> of reference costs<br />
- Help to dimensi<strong>on</strong>ing and investment decisi<strong>on</strong> for facilities programs ( storage, waste c<strong>on</strong>diti<strong>on</strong>ing facility,…)<br />
- Validati<strong>on</strong> of waste cost ratio.<br />
In this paper we will take Marcoule as a more precise example. On this CEA center, heavy operati<strong>on</strong>s of clean-up<br />
and decommissi<strong>on</strong>ing are carried out <strong>on</strong> the first French reprocessing plants –UP1-, and the related workshops.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>ses installati<strong>on</strong>s have been shut down in 1996. Since this date the main operati<strong>on</strong>s were focussed <strong>on</strong> definitive<br />
shutdown and dismantling of equipments which were to be realized in priority in the goal of reducing radiological<br />
activity and operating costs.<br />
Thus, the c<strong>on</strong>solidati<strong>on</strong> of the inventory data is essential to valid a scenario and then to design facilities for the<br />
following stages of the UP1 project.<br />
5) 40258 – Management of historical waste legacy at NRG Petten�<br />
Renate de Vos, Nuclear Research and c<strong>on</strong>sultancy Group (Netherlands)<br />
Since the 1960s, the Waste Storage Facility (WSF) in Petten has been used to store radioactive waste. In 1993, the<br />
Dutch government decided that all nuclear waste should be stored in the central storage facility COVRA (Dutch Central<br />
Organisati<strong>on</strong> for Radioactive Waste). This means that the drums with historical waste must all be opened, their c<strong>on</strong>tents<br />
sorted according to intermediate- and low-level radioactivity and subsequently packed for transport to the COVRA<br />
facility.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> intermediate-level radioactive waste processing Unit (HAVA-VU) has been designed specifically for this<br />
purpose.<br />
In this paper an overview will be given of the process of this HAVA-VU project in the last decade. Subsequently<br />
the current status and path forward will be described. Also the chosen soluti<strong>on</strong>s for waste processing and characterizati<strong>on</strong><br />
will be discussed.<br />
6) 40031 – Norwegian Support For Regulati<strong>on</strong>s Of Radioactive Waste Management From Uranium Mining<br />
And Mill Tailings In Central� Asia<br />
Tamara Zhunussova, Malgorzata Sneve, Astrid Liland, Norwegian Radiati<strong>on</strong> Protecti<strong>on</strong> Authority (Norway);<br />
Alexander Kim, Kazakhstan Atomic Energy Committee (Kazakhstan);<br />
Ulmas Mirsaidov, Tajikistan Nuclear and Radiati<strong>on</strong> Safety Agency (Tajikistan);<br />
Baigabyl Tol<strong>on</strong>gutov, Chui Ecological Laboratory of Kyrgiz Republic (Kyrgiz);<br />
Per Strand, Norwegian Radiati<strong>on</strong> Protecti<strong>on</strong> Authority, University of Life Sciences (UMB) (Norway)<br />
In Central Asia the radioactive waste comes mainly from uranium mining and milling, nuclear weap<strong>on</strong> testing and<br />
nuclear power development and other i<strong>on</strong>izing sources. This waste was produced, to a greater extent, by the<br />
military-industrial complex and the uranium and n<strong>on</strong>-uranium industry, and, to a lesser extent, by the nuclear industry<br />
and in the process of use of isotope products. Exploitati<strong>on</strong> and mining of uranium and thorium deposits produce a large<br />
amount of solid and liquid radioactive waste, as well volatile c<strong>on</strong>taminants which need a proper management. In Central<br />
Asia the wastes are mainly stored at the surface in large piles and represent a l<strong>on</strong>g-term potential health and<br />
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envir<strong>on</strong>mental hazard. <str<strong>on</strong>g>The</str<strong>on</strong>g> process of remediating legacy sites of the past and reducing the threats is now getting under<br />
way, with the design and implementati<strong>on</strong> of remediati<strong>on</strong> activities, partly with internati<strong>on</strong>al support. However, there is a<br />
significant lack in the regulatory basis for carrying out such remediati<strong>on</strong> work, including a lack of relevant radiati<strong>on</strong> and<br />
envir<strong>on</strong>mental safety norms and standards, licensing procedures and requirements for m<strong>on</strong>itoring etc., as well as<br />
expertise to transform such a basis into practice. Accordingly, the objective of the proposed project is to assist the<br />
relevant regulatory authorities in Kazakhstan, Kirgizstan and Tajikistan to develop nati<strong>on</strong>al robust and adequate<br />
regulati<strong>on</strong>s and procedures, taking into account the internati<strong>on</strong>al guidance and Norwegian experience in regulatory<br />
support projects in Russia. Specific expected results in the project period include: a threat assessment report identifying<br />
priority areas for regulatory development, based <strong>on</strong> the status of current regulatory documents and the hazard presented<br />
by the different sites and facilities; development of nati<strong>on</strong>al radioactive waste management strategies in each country;<br />
development of an enhanced regulatory framework.<br />
7) 40259 – Strengthening the Nuclear Security System of Central Radioactive Waste Processing and Storage<br />
Facility at AERE<br />
Abdus Sattar Mollah, Bangladesh Atomic Energy Commissi<strong>on</strong> (Bangladesh)<br />
In the aftermath of the events surrounding September 11, 2001, internati<strong>on</strong>al organizati<strong>on</strong>s have called up<strong>on</strong><br />
worldwide users and holders of radioactive material to increase security measures in order to prevent a loss of c<strong>on</strong>trol<br />
through acts of theft or sabotage. <str<strong>on</strong>g>The</str<strong>on</strong>g> universal c<strong>on</strong>cern is that unsecured material could end up in the possessi<strong>on</strong> of a<br />
terrorist group for the purpose of c<strong>on</strong>structing and det<strong>on</strong>ating a radiological dispersi<strong>on</strong> device or “dirty bomb”.<br />
Regardless of the security or risk classificati<strong>on</strong> criteria used, source material used in all categories of radioactive<br />
materials is categorized as requiring the highest level of protecti<strong>on</strong> to prevent unauthorized access and acquisiti<strong>on</strong>. In<br />
2006, the BAEC formalized specific protecti<strong>on</strong> requirements for all licensees of high strength radioactive materials<br />
within their jurisdicti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> basic requirements include establishing physical security perimeters, c<strong>on</strong>trolling and<br />
m<strong>on</strong>itoring access through those perimeters, and verifying that pers<strong>on</strong>s authorized access to the source material are<br />
trustworthy and reliable. <str<strong>on</strong>g>The</str<strong>on</strong>g> practical implementati<strong>on</strong> of these requirements necessitates the involvement of a security<br />
professi<strong>on</strong>al to provide guidance in the creati<strong>on</strong> and implementati<strong>on</strong> of a comprehensive facility security plan. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
following activities have been d<strong>on</strong>e to c<strong>on</strong>trolling access to the central radioactive processing and storage:<br />
• C<strong>on</strong>trol access into the facility building,<br />
• designating c<strong>on</strong>trol entrance points for employees, visitors and c<strong>on</strong>tractors,<br />
• equipping all perimeter egress-<strong>on</strong>ly doors with alarms,<br />
• requiring all dock doors to be closed or openings secured when not in use,<br />
• Additi<strong>on</strong>al access c<strong>on</strong>trol to the pers<strong>on</strong>nel entry door,<br />
• C<strong>on</strong>trol access to the source material.<br />
For the most part this is achieved through shield design and required safety interlock systems and alarms. <str<strong>on</strong>g>The</str<strong>on</strong>g> shield<br />
structure is substantial in both size and thickness, while entry or exit through the product portal is generally difficult. This<br />
paper presents approaches that may be used to improve nuclear security system at Central Radioactive Waste Processing<br />
and Storage Facility including increased vigilance, educati<strong>on</strong> and awareness, and physical changes to the facility.<br />
SESSION H1: : Nati<strong>on</strong>al and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Programs (1)<br />
1) 40097 – Overview of NUMO's policy for implementing safe geological disposal and developing supporting<br />
technologies<br />
Hiroyuki Tsuchi, Kenichi Kaku, Katsuhiko Ishiguro, Akira Deguchi, Yoshiaki Takahashi, NUMO (Japan)<br />
Based <strong>on</strong> the Act <strong>on</strong> Final Disposal of Specified Radioactive Waste (Final Disposal Act), the Nuclear Waste<br />
Management Organizati<strong>on</strong> of Japan (NUMO) was established in October 2000 as the implementing organizati<strong>on</strong> for<br />
geological disposal of high-level radioactive waste. In December 2002, NUMO issued a nati<strong>on</strong>wide call for volunteers to<br />
initiate the siting process. With the revisi<strong>on</strong> of the Final Disposal Act in 2007, some types of TRU waste were included<br />
as waste destined for geological disposal and thus fall within the remit of NUMO.<br />
NUMO has been developing the technologies required for implementati<strong>on</strong> of the project and has carried out a range of siting and<br />
performance assessment (PA) activities. However, no applicati<strong>on</strong> has been received as yet from a volunteer municipality. Together<br />
with the nati<strong>on</strong>al government, NUMO is now making increased efforts to obtain public acceptance for initiating literature surveys (the<br />
first step in the siting process). In this c<strong>on</strong>necti<strong>on</strong>, NUMO decided to prepare a 2010 technical report as a tool for improving the<br />
understanding of the geological disposal project by the stakeholders. <str<strong>on</strong>g>The</str<strong>on</strong>g> report will present the safety c<strong>on</strong>cept that describes how<br />
NUMO aims to achieve safe geological disposal through ca.100-year project and will document the progress made with developing the<br />
technologies that support the safety c<strong>on</strong>cept.<br />
Three policies for ensuring safety are followed by NUMO, namely a) staged project implementati<strong>on</strong> and decisi<strong>on</strong> making based<br />
<strong>on</strong> iterative c<strong>on</strong>firmati<strong>on</strong> of safety, b) project implementati<strong>on</strong> based <strong>on</strong> reliable technologies (or Best Available Technologies - BAT)<br />
and c) technical activities for building c<strong>on</strong>fidence in NUMO’s safety c<strong>on</strong>cept. One of the highlights of the report is the introducti<strong>on</strong> of<br />
a “roadmap” which includes all project milest<strong>on</strong>es, goals in each stage and main activities for achieving these goals. <str<strong>on</strong>g>The</str<strong>on</strong>g> roadmap is<br />
41
Abstracts<br />
also being used to identify the technologies required for implementing the geological disposal project, thus providing a guideline for<br />
evaluating currently available technologies and identifying needs for further technology development. <str<strong>on</strong>g>The</str<strong>on</strong>g> technologies developed to<br />
date and the plan for further technical development are explained in this paper.<br />
2) 40150 – Stepwise Site Selecti<strong>on</strong> in Switzerland - Sectoral Plan: Status and Outlook<br />
Thomas Ernst, Markus Fritschi, Stratis Vomvoris, Nagra (Switzerland)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> starting point is the nominati<strong>on</strong> of siting regi<strong>on</strong>s that fulfil the criteria for l<strong>on</strong>g-term safety and engineering<br />
feasibility defined in the Sectoral Plan. In October 2008, Nagra proposed a total of 6 siting regi<strong>on</strong>s for the LLW<br />
repository and three for the HLW repository; the latter would also be suitable for shared use with the surface facilities<br />
and part of the access tunnels for the two types of repositories.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> review of Nagra’s proposals by the safety authority (ENSI – the Swiss Federal Nuclear Safety Inspectorate) and<br />
its supporting commissi<strong>on</strong> was completed in February 2010. <str<strong>on</strong>g>The</str<strong>on</strong>g> decisi<strong>on</strong>-making process foresees evaluati<strong>on</strong> of the<br />
review and recommendati<strong>on</strong>s of ENSI by the various agencies at the governmental, cant<strong>on</strong>al and local level, an open<br />
public c<strong>on</strong>sultati<strong>on</strong> and finally, a resoluti<strong>on</strong> of the comments received by the Swiss Federal Office of Energy, a<br />
recommendati<strong>on</strong> to the Federal Government and a decisi<strong>on</strong> by the Federal Government.<br />
At the same time, the procedures and guidelines for the selecti<strong>on</strong> of the (at least) two potential sites for each of the<br />
repositories are being finalised by the safety authorities. Although the safety and engineering criteria remain the same,<br />
Stage 2 foresees a provisi<strong>on</strong>al safety analysis for each potential site as <strong>on</strong>e of the criteria to be used in the site selecti<strong>on</strong><br />
process.<br />
This paper will highlight the main findings of the review by the authorities and Nagra’s resp<strong>on</strong>se to issues raised.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> next steps and preparatory activities for the initiati<strong>on</strong> of Stage 2 will also be described, as well as how the criteria<br />
and guidelines specified by ENSI will be applied by Nagra in order to meet the requirements for a successful completi<strong>on</strong><br />
of Stage 2.<br />
3) 40084 – Site Selecti<strong>on</strong> for a Geological Disposal in France: an Approach of C<strong>on</strong>vergence<br />
Gerald� Ouzounian, Roberto Miguez, Jean-Louis Tis<strong>on</strong>, Andra (France)<br />
On December 1991, the French Nati<strong>on</strong>al Assembly passed the French Waste Management Research Act,<br />
authorizing a 15 year research program of three opti<strong>on</strong>s for HLW: separati<strong>on</strong> and/or transmutati<strong>on</strong>, l<strong>on</strong>g-term storage,<br />
and geologic disposal. On June 2006, the “Planning Act <strong>on</strong> the sustainable management of radioactive materials and<br />
waste" sets a new framework and new aims to the above menti<strong>on</strong>ed opti<strong>on</strong>s.<br />
This paper deals <strong>on</strong>ly with the geologic disposal research program. In a step by step approach, this program has<br />
been broken down into three phases having intermediate goals : site selecti<strong>on</strong> for an Underground research Laboratory<br />
(URL), potential disposal feasibility, potential reversible disposal design.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> first step of the research program aimed at URL site selecti<strong>on</strong>. From 1994 to 1996, Andra carried out<br />
geological-characterizati<strong>on</strong> work in four departments. This enabled to make the Request for Licensing and Operati<strong>on</strong> of<br />
the laboratory facility <strong>on</strong> three sites. During this phase, wells, 2D seismic campaigns and land studies of geologic<br />
outcrops were the essential activities. <str<strong>on</strong>g>The</str<strong>on</strong>g> result was the selecti<strong>on</strong> of the most suitable site for the implementati<strong>on</strong> of an<br />
underground laboratory. Main results <strong>on</strong> Bure URL will be presented in the paper.<br />
In the sec<strong>on</strong>d phase the research program targeted the safety and technical feasibility of a potential reversible<br />
disposal somewhere in Meuse and Haute Marne D departments site, chosen by the government in 1998. Andra c<strong>on</strong>ducted<br />
geologic survey during the URL shaft c<strong>on</strong>structi<strong>on</strong> and experiments in drifts at depths of 445 and 490 m. This program<br />
allowed c<strong>on</strong>solidating the knowledge already acquired: geological envir<strong>on</strong>ment, stability of the rock, c<strong>on</strong>tainment<br />
properties and it c<strong>on</strong>firms that the rock will maintain its qualities. <str<strong>on</strong>g>The</str<strong>on</strong>g> 2005 Progress Report presents the results of this<br />
phase. <str<strong>on</strong>g>The</str<strong>on</strong>g> main c<strong>on</strong>clusi<strong>on</strong> is that a potential disposal facility may be safely c<strong>on</strong>structed over a z<strong>on</strong>e around the URL,<br />
called transpositi<strong>on</strong> z<strong>on</strong>e (about250 km2). <str<strong>on</strong>g>The</str<strong>on</strong>g> paper will present the most important results in this phase.<br />
From 2006, the third phase of the program, the activities were oriented, inside the transpositi<strong>on</strong> z<strong>on</strong>e, to determine a<br />
smaller z<strong>on</strong>e in which à potential disposal facility could be designed. In 2009, Andra reported to the French authorities a<br />
proposal describing such a z<strong>on</strong>e. In this paper the main results of this phase will be presented. Finally, next steps towards<br />
a final implementati<strong>on</strong> will be given.<br />
SESSION H2: Transportati<strong>on</strong>, Storage and Waste Treatment<br />
1) 40155 – Support of the Nuclear Research Institute Rez plc of the Shipment of Spent Nuclear Fuel from<br />
Research Reactors to the Russian Federati<strong>on</strong> for Reprocessing in the Frame of the RRRFR Program<br />
Josef Podlaha, Karel Svoboda, Nuclear research institute plc. (Czech Republic)<br />
In 2007, spent nuclear fuel (SNF) from the Nuclear Research Institute Rez plc (NRI) was shipped to the Russian<br />
Federati<strong>on</strong> for reprocessing. A large amount of SNF of Russian origin has been accumulated after 50 years of research<br />
reactor operati<strong>on</strong>.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> shipment was realized in the frame of the Russian Research Reactor Fuel Return (RRRFR) program under the<br />
42
Abstracts<br />
US-Russian Global Threat Reducti<strong>on</strong> Initiative (GTRI). SNF shipment from NRI to the Russian Federati<strong>on</strong> (RF)<br />
represented a very complex and complicated technical, legal and c<strong>on</strong>tractual scope of work.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> SNF shipment has been realized under specific c<strong>on</strong>diti<strong>on</strong>s: 1. High capacity SKODA VPVR/M casks were used<br />
for transportati<strong>on</strong> for the first time. 2. For the first time, high enriched uranium SNF from a research reactor has been sent<br />
to the RF from a European Uni<strong>on</strong> country under the appropriate intergovernmental agreements, legal regulati<strong>on</strong>s and<br />
c<strong>on</strong>diti<strong>on</strong>s.<br />
NRI also participates in shipments of SNF from other countries within the framework of the RRRFR program.<br />
NRI`s participati<strong>on</strong> c<strong>on</strong>sists of: - SKODA VPVR/M casks leasing, including service and maintenance inspecti<strong>on</strong>s of the<br />
casks, - transportati<strong>on</strong> of the casks to the research reactor site, -providing cask documentati<strong>on</strong> in support of development<br />
of licenses, certificates, etc. for authorizati<strong>on</strong> of the shipment, - training of pers<strong>on</strong>nel in cask use and SNF loading, -<br />
technical oversight and expertise during the cask handling, fuel loading and cask closing and sealing, - the drying and<br />
helium leak testing of casks, -the return transportati<strong>on</strong> of the empty casks from the Russian/Ukrainian border to NRI.<br />
NRI participated in shipments of SNF from Bulgaria and Hungary in 2008, from Poland in 2009 and 2010 adn from<br />
Ukraine in 2010. Shipments from Belarus and Serbia are planned in 2010. <str<strong>on</strong>g>The</str<strong>on</strong>g> sec<strong>on</strong>d shipment of the residue of high<br />
enriched SNF from NRI after changeover of the reactor operati<strong>on</strong> to low enriched fuel will be implemented in 2013.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> experiences gained during the SNF transportati<strong>on</strong> are described in the paper together with the present and<br />
future NRI activities in support of the SNF shipment from other countries.<br />
2) 40177 – L<strong>on</strong>g Term Storage of Nuclear Spent Fuel as Key Role of Japan's Nuclear Fuel Cycle until 2100:<br />
Cost and Benefit<br />
Tadahiro Katsuta, Meiji University (Japan)<br />
Political and technical advantages to introduce spent nuclear fuel interim storage into Japan's nuclear fuel cycle are<br />
examined. Once Rokkasho reprocessing plant starts to be operated, 80,000 tHM of spent Low Enriched Uranium (LEU)<br />
fuel must be stored in an Away From Reactor (AFR) interim storage site until 2100. If a following reprocessing plant<br />
starts the operati<strong>on</strong>, the Spent LEU reaches its peak of 30,000 tHM before 2050, and then decreases until the end of the<br />
following reprocessing plant operati<strong>on</strong>. Throughput of the following reprocessing plant is assumed as twice of Rokassho<br />
reprocessing plant case, namely 1,600tHM/year. On the other hand, three times of final disposal site of High Level<br />
Nuclear Waste (HLW) will be necessary with this c<strong>on</strong>diti<strong>on</strong>. Besides, large amount of plut<strong>on</strong>ium surplus will occur, even<br />
if First Breeder Reactors (FBR)s c<strong>on</strong>sume the plut<strong>on</strong>ium. <str<strong>on</strong>g>The</str<strong>on</strong>g> maximum of plut<strong>on</strong>ium surplus will reach almost 500 t<strong>on</strong>s<br />
of plut<strong>on</strong>ium. <str<strong>on</strong>g>The</str<strong>on</strong>g>se results indicate that current nuclear policy does not solve the spent fuel problems but even<br />
complicate them. Thus, reprocessing policy could put off the problems in spent fuel interim storage capacity and other<br />
fears could appear such as difficulties in large amount of HLW final disposal management or separated plut<strong>on</strong>ium<br />
management. If there is no reprocessing or MOX use, the amount of spent fuel will reach over 115,000 t<strong>on</strong>es at the year<br />
of 2100. However, the spent fuel management could be simplified and also the cost and the security would be improved<br />
by using an interim storage primarily.<br />
3) 40285 – TRU Recycling Opti<strong>on</strong>s for increasing Protected Plut<strong>on</strong>ium Producti<strong>on</strong> of FBR<br />
Sidik Permana, Mitsutoshi Suzuki, JAEA (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> embodied challenges for introducing closed fuel cycle are utilizing advanced fuel reprocessing and fabricati<strong>on</strong><br />
facilities as well as nuclear n<strong>on</strong>proliferati<strong>on</strong> aspect. Optimizati<strong>on</strong> target of advanced reactor design should be maintained<br />
properly to obtain high performance of safety, fuel breeding and reducing some l<strong>on</strong>g-lived and high level radioactivity of<br />
spent fuel by closed fuel cycle opti<strong>on</strong>s. In this paper, the c<strong>on</strong>tributi<strong>on</strong> of loading trans-uranium to the core performance,<br />
fuel producti<strong>on</strong>, and reducti<strong>on</strong> of minor actinide in high level waste (HLW) have been investigated during reactor<br />
operati<strong>on</strong> of large fast breeder reactor (FBR). Excess reactivity can be reduced by loading some minor actinide in the<br />
core which affect to the increase of fuel breeding capability, however, some small reducti<strong>on</strong> values of breeding capability<br />
are obtained when minor actinides are loaded in the blanket regi<strong>on</strong>s. As a total compositi<strong>on</strong>, MA compositi<strong>on</strong>s are<br />
reduced by increasing operati<strong>on</strong> time. Relatively smaller reducti<strong>on</strong> value was obtained at end of operati<strong>on</strong> by blanket<br />
regi<strong>on</strong>s (9 %) than core regi<strong>on</strong>s (15 %). In additi<strong>on</strong>, adopting closed cycle of MA obtains better intrinsic aspect of<br />
nuclear n<strong>on</strong>proliferati<strong>on</strong> based <strong>on</strong> the increase of even mass plut<strong>on</strong>ium in the isotopic plut<strong>on</strong>ium compositi<strong>on</strong>.<br />
4) 40132 – Transuranic (TRU) Waste Volume Reducti<strong>on</strong> Operati<strong>on</strong> at a Plut<strong>on</strong>ium Facility<br />
Michael Cournoyer, Archie E. Nix<strong>on</strong>, Keith W. Fife, Arnold M. Sandoval,<br />
Vincent E. Garcia, Robert L. Dodge, LANL (USA)<br />
Programmatic operati<strong>on</strong>s at the Los Alamos Nati<strong>on</strong>al Laboratory Plut<strong>on</strong>ium Facility (TA-55) involve working with<br />
various amounts of plut<strong>on</strong>ium and other highly toxic, alpha-emitting materials. <str<strong>on</strong>g>The</str<strong>on</strong>g> spread of radiological c<strong>on</strong>taminati<strong>on</strong><br />
<strong>on</strong> surfaces, airborne c<strong>on</strong>taminati<strong>on</strong>, and excursi<strong>on</strong>s of c<strong>on</strong>taminants into the operator’s breathing z<strong>on</strong>e are prevented<br />
through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides<br />
primary c<strong>on</strong>finement). Size-reducti<strong>on</strong> operati<strong>on</strong>s <strong>on</strong> glovebox equipment are a comm<strong>on</strong> activity when a process has been<br />
disc<strong>on</strong>tinued and the room is being modified to support a new customer. <str<strong>on</strong>g>The</str<strong>on</strong>g> Actinide Processing Group at TA-55 uses<br />
<strong>on</strong>e-meter or l<strong>on</strong>ger glass columns to process plut<strong>on</strong>ium. Disposal of used columns is a challenge, since they must be<br />
43
Abstracts<br />
size-reduced to get them out of the glovebox. <str<strong>on</strong>g>The</str<strong>on</strong>g> task is a high-risk operati<strong>on</strong> because the glass shards that are generated<br />
can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker’s skin when completing the task. One<br />
of the Less<strong>on</strong>s Learned from these operati<strong>on</strong>s is that Laboratory management should critically evaluate each hazard and<br />
provide more effective measures to prevent pers<strong>on</strong>nel injury. A bag made of puncture-resistant material was <strong>on</strong>e of these<br />
enhanced c<strong>on</strong>trols. We have investigated the effectiveness of these bags and have found that they safely and effectively<br />
permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into<br />
a c<strong>on</strong>tainer for removal from the glovebox as n<strong>on</strong>-compactable transuranic (TRU) waste. This size-reducti<strong>on</strong> operati<strong>on</strong><br />
reduces solid TRU waste volume generati<strong>on</strong> by almost 2½ times. Replacing <strong>on</strong>e-time-use bag-out bags with multiple-use<br />
glass crushing bags also c<strong>on</strong>tributes to reducing generated waste. In additi<strong>on</strong>, significant costs from c<strong>on</strong>taminati<strong>on</strong>,<br />
cleanup, and preparati<strong>on</strong> of incident documentati<strong>on</strong> are avoided. This effort c<strong>on</strong>tributes to the Los Alamos Nati<strong>on</strong>al<br />
Laboratory C<strong>on</strong>tinuous Improvement Program by improving the efficiency, cost-effectiveness, and formality of glovebox<br />
operati<strong>on</strong>s. In this report, the technical issues, associated with implementing this process improvement are addressed, the<br />
results discussed, effectiveness of Less<strong>on</strong>s Learned evaluated, and waste savings presented.<br />
5) 40247 – Dispositi<strong>on</strong> of Transuranic Residues from Plut<strong>on</strong>ium Isentropic Compressi<strong>on</strong> Experiment (Pu-ICE).<br />
LA-UR 10-04699.<br />
Kapil Goyal, David M. French, LANL (USA); Betty J. Humphrey, West<strong>on</strong> Soluti<strong>on</strong>s, Inc. (USA);<br />
Jeffry Gluth, Sandia Nati<strong>on</strong>al Laboratories/NM (USA)<br />
In 1992, the U.S. C<strong>on</strong>gress passed legislati<strong>on</strong> to disc<strong>on</strong>tinue above- and below-ground testing of nuclear weap<strong>on</strong>s.<br />
Because of this, the U.S. Department of Energy (DOE) must rely <strong>on</strong> laboratory experiments and computer-based<br />
calculati<strong>on</strong>s to verify the reliability of the nati<strong>on</strong>’s nuclear stockpile. <str<strong>on</strong>g>The</str<strong>on</strong>g> Sandia Nati<strong>on</strong>al Laboratories/New Mexico<br />
(SNL/NM) Z machine was developed by the DOE to support its science-based approach to stockpile stewardship.<br />
SNL/NM researchers also use the Z machine to test radiati<strong>on</strong> effects <strong>on</strong> various materials in experiments designed<br />
to mimic nuclear explosi<strong>on</strong>s. Numerous comp<strong>on</strong>ents, parts, and materials have been tested. <str<strong>on</strong>g>The</str<strong>on</strong>g>se experiments use a<br />
variety of radi<strong>on</strong>uclides; however, plut<strong>on</strong>ium (Pu) isotopes with greater than ninety-eight percent enrichment are the<br />
primary radi<strong>on</strong>uclides used in the experiments designed for stockpile stewardship. In May 2006, SNL/NM received<br />
authority that the Z Machine Isentropic Compressi<strong>on</strong> Experiments could commence.<br />
Los Alamos Nati<strong>on</strong>al Laboratory (LANL) provided the plut<strong>on</strong>ium targets and loaded the target assemblies, which<br />
were fabricated by SNL/NM. LANL shipped the loaded assemblies to SNL/NM for Z machine experiments. Three<br />
experiments were c<strong>on</strong>ducted from May through July 2006. <str<strong>on</strong>g>The</str<strong>on</strong>g> residues from each experiment, which weighed up to 913<br />
pounds, were metallic and packaged into a respective 55-gall<strong>on</strong> drum each. Based <strong>on</strong> a memorandum of understanding<br />
between the two laboratories, LANL provides the plut<strong>on</strong>ium samples and the respective radio-isotopic informati<strong>on</strong>.<br />
SNL/NM c<strong>on</strong>ducts the experiments and provides temporary storage for the drums until shipment to LANL for final waste<br />
certificati<strong>on</strong> for disposal at the Waste Isolati<strong>on</strong> Pilot Plant (WIPP) in southeastern New Mexico. This paper presents a<br />
comprehensive approach for documenting generator knowledge for characterizati<strong>on</strong> of waste in cooperati<strong>on</strong> with<br />
scientists at the two laboratories and addresses a variety of topics such as material c<strong>on</strong>trol and accountability, safeguards<br />
of material, terminati<strong>on</strong> of safeguards for eventual shipment from SNL/NM to LANL, associated approvals from<br />
DOE-Carlsbad Field Office, which governs WIPP and various notificati<strong>on</strong>s. It portrays a comprehensive approach<br />
needed for successful completi<strong>on</strong> of a complex project between two nati<strong>on</strong>al laboratories.<br />
6) 40188 – A Milest<strong>on</strong>e in Vitrificati<strong>on</strong> - the Replacement of a Hot Metallic Crucible with a Cold Crucible<br />
Melter in a Hot Cell at the La Hague Plant<br />
Sphiee Robert, Benoit Carpentier,SGN (France); Florence Gassot Guilbert, SGN Service procédé (France);<br />
Sandrine Naline, AREVA (France); Frédéric Gouyaud, AREVA NC (France); Christophe Girold, CEA (France)<br />
Vitrificati<strong>on</strong> of high-level waste is the internati<strong>on</strong>ally recognized way to optimize the c<strong>on</strong>diti<strong>on</strong>ed High Level Waste<br />
to be disposed of.<br />
AREVA’s successful operati<strong>on</strong> of AVM at the Marcoule plant, R7 and T7 at the La Hague Plants dem<strong>on</strong>strates the<br />
capabilities and experience of the Group to deploy innovative high level waste (HLW) processing technologies in<br />
industrial facilities, in partnership with R&D (CEA) and AREVA engineering (SGN). CEA and AREVA engineering<br />
team have c<strong>on</strong>tinuously improved the hot metallic crucible melter vitrificati<strong>on</strong> technology through operati<strong>on</strong>al feedback<br />
aswell as <strong>on</strong>going research and developement. <str<strong>on</strong>g>The</str<strong>on</strong>g>y have led the way in the development and implementati<strong>on</strong> of Cold<br />
Crucible Inducti<strong>on</strong> Melter technology (CCIM).<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> cold crucible is a compact water-cooled melter in which the radioactive waste and the glass are molten by direct<br />
high frequency inducti<strong>on</strong>. This technology can handle with highly corrosive soluti<strong>on</strong>s and high operating temperature,<br />
which offers, am<strong>on</strong>g others advantages: o a great flexibility in matrix compositi<strong>on</strong>s, o the increase of the industrial glass<br />
producti<strong>on</strong> capacity, ° increase of melting temperature, ° allow higher waste loading, ° extend to a wide and varied waste<br />
types<br />
In order to take advantage of CCIM, a new project, called “Vitrificati<strong>on</strong> 2010”, was launched in 2005 with the<br />
objective to put in commercial operati<strong>on</strong> a CCIM in <strong>on</strong>e of the existing and active R7 vitrificati<strong>on</strong> line in 2010. <str<strong>on</strong>g>The</str<strong>on</strong>g> main<br />
challenge for the project team is to replace the hot metallic crucible melter with the CCIM: o in an existing hot cell which<br />
is in operati<strong>on</strong> for 20 years with high level waste soluti<strong>on</strong>s, o with respect to the current hot cell’s layout (calciner,<br />
through-wall for utility for example…).<br />
44
Abstracts<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper will illustrate why this event is a major milest<strong>on</strong>e in vitrificati<strong>on</strong> and how the “Vitrificati<strong>on</strong> 2010” project<br />
succeeds in record time and without any impact <strong>on</strong> the La Hague Plant producti<strong>on</strong>.<br />
7) 40265 – Adaptati<strong>on</strong> of CCIM technology for HLW treatment. Results of research and development<br />
Vladimir Lebedev, Alexander Kobelev, Fyodor Lifanov, Sergey Dmitriev, SIA Rad<strong>on</strong> (Russia)<br />
Results of research of possibility of Cold Crucible Inductive Melter (CCIM) technology applicati<strong>on</strong> for HLW<br />
treatment (<strong>on</strong> examples of Savannah River (USA) HLW and PA “Mayak” (Russia) HLW), carried out in Moscow SIA<br />
RADON, and also results of development of new perspective facility for appliance in lab scale and then for real HLW<br />
treatment, are shown in this report. From 2003 till 2010 the research of possibility of different HLW treatment with<br />
CCIM technology are carried out. <str<strong>on</strong>g>The</str<strong>on</strong>g> principal possibility of vitrificati<strong>on</strong> of wastes with different compositi<strong>on</strong>s in the<br />
cold crucible was shown. <str<strong>on</strong>g>The</str<strong>on</strong>g> features of appliance of various materials, natural and industrially produced, as glass<br />
forming and modifying additi<strong>on</strong>s were explored. Charge compositi<strong>on</strong>s, made with using each researched sample of HLW<br />
imitator, were formulated and maximal HLW c<strong>on</strong>taining in charge was determined. <str<strong>on</strong>g>The</str<strong>on</strong>g>n the samples of glass obtained<br />
were explored. <str<strong>on</strong>g>The</str<strong>on</strong>g> main technological features of melting process were determined and principals of organizati<strong>on</strong> and<br />
c<strong>on</strong>trol of the process were formulated. <str<strong>on</strong>g>The</str<strong>on</strong>g> pattern of cold crucible for HLW imitators treatment being included in<br />
experimental stand in PA “Mayak” was created. Also the System of Automatic C<strong>on</strong>trol for crucible was created. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
tests and research of equipment work were carried out. On the base of analysis of data gained earlier and newly obtained<br />
the main requirements to designing of inductive melters and additi<strong>on</strong>al equipment, intended for real HLW treatment,<br />
were worked out. <str<strong>on</strong>g>The</str<strong>on</strong>g>se requirements seem like a part of Task for designing of experimental-industrial HLW treatment<br />
plant, that is c<strong>on</strong>templated to built in PA “Mayak” in nearest time.<br />
SESSION H3: Panel "Radwaste Human Resource Development to Support the Nuclear Renaissance"<br />
Abstract Not Required<br />
SESSION D1 : Nati<strong>on</strong>al and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> D&D Programs<br />
1) 40003 – Westinghouse PWR and BWR Reactor Vessel Segmentati<strong>on</strong> Experience in Using Mechanical<br />
Cutting Process<br />
Joseph Boucau, Stefan Fallström, Per Segerud, Paul Kreitman, Westinghouse Electric Belgium (Belgium)<br />
Some commercial nuclear power plants have been permanently shut down to date and decommissi<strong>on</strong>ed using<br />
dismantling methods. Other operating plants have decided to undergo an upgrade process that includes replacement of<br />
reactor internals. In both cases, there is a need to perform a segmentati<strong>on</strong> of the reactor vessel internals with proven<br />
methods for l<strong>on</strong>g term waste disposal. Westinghouse has developed several c<strong>on</strong>cepts to dismantle reactor internals based<br />
<strong>on</strong> safe and reliable techniques, including plasma arc cutting (PAC), abrasive waterjet cutting (AWJC), metal<br />
disintegrati<strong>on</strong> machining (MDM), or mechanical cutting. Mechanical cutting has been used by Westinghouse since 1999<br />
for both PWR’s and BWR’s and its process has been c<strong>on</strong>tinuously improved over the years. This paper will describe the<br />
sequential steps required to segment, separate, and package each individual comp<strong>on</strong>ent, based <strong>on</strong> this mechanical cutting<br />
method. Detailed planning is essential to a successful project, and typically a “Segmentati<strong>on</strong> and Packaging Plan” is<br />
prepared to document the effort. <str<strong>on</strong>g>The</str<strong>on</strong>g> usual method is to start at the end of the process, by evaluating the waste disposal<br />
requirements imposed by the waste disposal agency, what type and size of c<strong>on</strong>tainers are available for the different<br />
disposal opti<strong>on</strong>s, and working backwards to select the best cutting tools and finally the cut geometry required. <str<strong>on</strong>g>The</str<strong>on</strong>g>se<br />
plans are made utilizing advanced 3-D CAD software to model the process. Another area where the modeling has proven<br />
invaluable is in determining the logistics of comp<strong>on</strong>ent placement and movement in the reactor cavity, which is typically<br />
very c<strong>on</strong>gested when all the internals are out of the reactor vessel in various stages of segmentati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> main objective<br />
of the segmentati<strong>on</strong> and packaging plan is to determine the strategy for separating the highly activated comp<strong>on</strong>ents from<br />
the less activated material, so that they can be disposed of in the most cost effective manner. Usually, highly activated<br />
comp<strong>on</strong>ents cannot be shipped off-site, so they must be packaged such that they can be dry stored with the spent fuel in<br />
an Independent Spent Fuel Storage Installati<strong>on</strong> (ISFSI). Less activated comp<strong>on</strong>ents can be shipped to an off-site disposal<br />
site depending <strong>on</strong> space availability. Several of the plants dismantled to date in the US have repackaged the less activated<br />
waste back into the reactor vessel and shipped the entire assembly to the disposal site. Decisi<strong>on</strong>s like these can be driven<br />
by many factors such as disposal costs, transportati<strong>on</strong> logistics, licensing fees, etc., but will have a significant impact <strong>on</strong><br />
the segmentati<strong>on</strong> and packaging plan so they must be c<strong>on</strong>sidered early in the planning phase. All segmentati<strong>on</strong> tools are<br />
remotely c<strong>on</strong>trolled since the mechanical segmentati<strong>on</strong> projects that Westinghouse has executed, so far, have been<br />
performed under water due to the high radiati<strong>on</strong> levels. ALARA and pers<strong>on</strong>al safety is the number <strong>on</strong>e priority during the<br />
site work. <str<strong>on</strong>g>The</str<strong>on</strong>g> complexity of the work requires well designed and reliable tools. Westinghouse has optimized the<br />
technologies from its experiences accumulated over the years. Its main focus has always been to improve tool handling<br />
and cutting speed, water cleanliness, fail-safe and safety aspects. Different band saws, disc saws, tube cutters and<br />
45
Abstracts<br />
shearing tools have been developed to cut the reactor internals. All of those equipments are hydraulically driven which is<br />
very suitable for submerged applicati<strong>on</strong>s. Mechanical cutting has a number of advantages compared to other cutting<br />
techniques. ? <str<strong>on</strong>g>The</str<strong>on</strong>g> technique produces almost no sec<strong>on</strong>dary waste. ? <str<strong>on</strong>g>The</str<strong>on</strong>g> visibility during cutting is very good because the<br />
cutting produces <strong>on</strong>ly a negligible amount of micro particles. ? Chips from the cutting process falls down to the bottom of<br />
the cutting pool and are easy to collect. ? No gases are produced that can cause airborne c<strong>on</strong>taminati<strong>on</strong>. ? <str<strong>on</strong>g>The</str<strong>on</strong>g> technique<br />
is safe and reliable. ? All reactor internal sizes, materials and thicknesses can be cut.<br />
Westinghouse experience in mechanical cutting has dem<strong>on</strong>strated that it is an excellent technique for segmentati<strong>on</strong><br />
of internals. Westinghouse c<strong>on</strong>tinues to develop new methods and products in order to further reduce the waste volume.<br />
In summary, the purpose of this paper will be to provide an overview of the Westinghouse mechanical segmentati<strong>on</strong><br />
process, based <strong>on</strong> actual experience from the work that has been completed to date.<br />
2) 40130 – EPRI Nuclear Power Plant Decommissi<strong>on</strong>ing Technology Program<br />
Karen Kim, Sean Bushart, Mike Naught<strong>on</strong>, Richard McGrath, Electrict Power Research Institute (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Electric Power Research Institute (EPRI) is a n<strong>on</strong>-profit research organizati<strong>on</strong> that supports the energy industry.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Nuclear Power Plant Decommissi<strong>on</strong>ing Technology Program c<strong>on</strong>ducts research and develops technology for the safe<br />
and efficient decommissi<strong>on</strong>ing of nuclear power plants.<br />
Several USA nuclear power plants shut down and entered active decommissi<strong>on</strong>ing in the 1990s. At that time the<br />
decommissi<strong>on</strong>ing of a commercial nuclear power plant was a first of a kind evoluti<strong>on</strong>; nuclear power plant<br />
decommissi<strong>on</strong>ing is a combinati<strong>on</strong> of industrial decommissi<strong>on</strong>ing with the complexities of radioactive materials and<br />
waste management. <str<strong>on</strong>g>The</str<strong>on</strong>g> first plants to undergo this process encountered various challenges related to decommissi<strong>on</strong>ing<br />
planning and project management, removal of large radioactive comp<strong>on</strong>ents, radiati<strong>on</strong> protecti<strong>on</strong>, site remediati<strong>on</strong>, final<br />
status survey, and license terminati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> USA regulatory framework for nuclear power plant decommissi<strong>on</strong>ing<br />
developed and evolved al<strong>on</strong>g with these first decommissi<strong>on</strong>ing projects. As of 2009 these nuclear power plants have<br />
successfully completed decommissi<strong>on</strong>ing activities and have achieved license terminati<strong>on</strong>. Two major c<strong>on</strong>tributors to the<br />
successful completi<strong>on</strong> of these projects were a) the development of technology specifically tailored to tasks unique to<br />
nuclear plant decommissi<strong>on</strong>ing and b) learning from each other’s experiences.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> EPRI Nuclear Power Plant Decommissi<strong>on</strong>ing Technology Program c<strong>on</strong>ducts research and develops technology<br />
that addresses the range of decommissi<strong>on</strong>ing tasks from pre-planning, site characterizati<strong>on</strong>, removal of large comp<strong>on</strong>ents,<br />
site remediati<strong>on</strong>, to license terminati<strong>on</strong>. A key feature of the EPRI Program is the collecti<strong>on</strong> and transfer of less<strong>on</strong>s<br />
learned and experiences from the major decommissi<strong>on</strong>ing projects c<strong>on</strong>ducted to date. <str<strong>on</strong>g>The</str<strong>on</strong>g> EPRI Program c<strong>on</strong>ducts<br />
research and development based <strong>on</strong> the needs of its utility members; the EPRI Program membership c<strong>on</strong>sists of utilities<br />
from the USA, France, Spain, Sweden, Italy, Taiwan, and Japan. EPRI is the mechanism through which these<br />
internati<strong>on</strong>al utilities can c<strong>on</strong>duct collaborative research and development and learn from each other’s experiences and<br />
less<strong>on</strong>s learned. In additi<strong>on</strong> to collaborative research and development, the EPRI Program Team of decommissi<strong>on</strong>ing<br />
experts provides direct and site-specific support to its member utilities to facilitate knowledge transfer and<br />
decommissi<strong>on</strong>ing project optimizati<strong>on</strong>.<br />
This presentati<strong>on</strong> will provide informati<strong>on</strong> about the EPRI Nuclear Power Plant Decommissi<strong>on</strong>ing Technology<br />
Program and discuss USA and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Decommissi<strong>on</strong>ing experiences to date.<br />
3) 40253 – Tokai-1 Decommissi<strong>on</strong>ing Project<br />
Keizaburou Yoshino , JAPC (Japan)<br />
Tokai-1 is the oldest and historical commercial Magnox reactor in Japan, which had started commercial operati<strong>on</strong> in<br />
1966. <str<strong>on</strong>g>The</str<strong>on</strong>g> unit had helped introducti<strong>on</strong> and establishment of the c<strong>on</strong>structi<strong>on</strong> and operati<strong>on</strong> technologies regarding<br />
nuclear power plant at early stage in Japan by its c<strong>on</strong>structi<strong>on</strong> and operating experiences. However, <str<strong>on</strong>g>The</str<strong>on</strong>g> Japan Atomic<br />
Power Company (JAPC), the operator and owner of Tokai-1, decided to cease its operati<strong>on</strong> permanently because of a<br />
fulfillment of its missi<strong>on</strong> and ec<strong>on</strong>omical reas<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> unit was finally ceased in March 1998 after about 32 year operati<strong>on</strong>.<br />
It took about three years for removal of all spent fuels from the site, and then decommissi<strong>on</strong>ing started in 2001. JAPC,<br />
always <strong>on</strong> the forefr<strong>on</strong>t of the nati<strong>on</strong>’s nuclear power generati<strong>on</strong>, is now grappling Japan’s first decommissi<strong>on</strong>ing of a<br />
commercial nuclear power plant, striving to establish effective, advanced decommissi<strong>on</strong>ing. <str<strong>on</strong>g>The</str<strong>on</strong>g> decommissi<strong>on</strong>ing for<br />
Tokai-1 was scheduled as 20 years project. At the beginning, the reactor was started to be in a static c<strong>on</strong>diti<strong>on</strong> for ten<br />
years (“safe storage period”). While the reactor had been safely stored, the phased decommissi<strong>on</strong>ing works started from<br />
n<strong>on</strong>-radioactive or low radioactive equipments toward high radioactive equipments. First five years of the project, JAPC<br />
c<strong>on</strong>centrated to drain and clean spent fuel cartridge cooling p<strong>on</strong>d and to remove c<strong>on</strong>venti<strong>on</strong>al equipments such as turbine,<br />
feed water pump and fuel charge machine as planed and budgeted.<br />
From 2006, the project came into new phase. JAPC has been trying to remove four Steam Raising Units (SRUs).<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> SRUs are huge comp<strong>on</strong>ent (7t<strong>on</strong>, �6.3m, H24.7m) of the Gas Cooling Reactor (GCR) and inside of the SRUs are<br />
radioactively c<strong>on</strong>taminated. It is c<strong>on</strong>cerned that workers are required safety and minimizing c<strong>on</strong>taminati<strong>on</strong> areas during<br />
SRU removal. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, JAPC is developing and introducing Jack-down method and remote c<strong>on</strong>trol multi functi<strong>on</strong>al<br />
removal system. This method is the method by which to remove the SRUs in turn from the bottom by lifting the SRU by<br />
a large jack and cutting for removing SRU is d<strong>on</strong>e remotely with this system. <str<strong>on</strong>g>The</str<strong>on</strong>g> system enables cutting and holding not<br />
<strong>on</strong>ly SRU body but also internals. This technology and experiences would be useful for the reactor removal in the near<br />
future.<br />
46
Abstracts<br />
4) 40289 – Activities of the OECD/NEA WPDD in the Field of Decommissi<strong>on</strong>ing<br />
Claudio Pescatore, Patrick O'Sullivan, OECD/NEA<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> OECD/NEA seeks to assist its member countries in developing strategies for the management of all types of<br />
radioactive material, including waste, that are safe and sustainable and that meet the broad needs of society - with<br />
particular emphasis <strong>on</strong> the management of l<strong>on</strong>g-lived waste and spent fuel and <strong>on</strong> decommissi<strong>on</strong>ing of disused nuclear<br />
facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g> programme of work in the area of decommissi<strong>on</strong>ing is supervised by the Radioactive Waste Management<br />
Committee (RWMC) and carried out by the Working Party <strong>on</strong> Decommissi<strong>on</strong>ing and Dismantling (WPDD). <str<strong>on</strong>g>The</str<strong>on</strong>g> latter is<br />
made of senior representatives from regulatory authorities, decommissi<strong>on</strong>ing organisati<strong>on</strong>s, policy making bodies, and<br />
researchand-development instituti<strong>on</strong>s from the NEA countries. It includes also representatives of the IAEA and of the the<br />
European Commissi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> WPDD supports the RWMC by keeping under review the policy, strategic, and regulatory<br />
aspects of decommissi<strong>on</strong>ing of phased-out nuclear installati<strong>on</strong>s. Its scope of work includes decommissi<strong>on</strong>ing and<br />
dismantling of shutdown facilities up to and including the release of the site, but excluding fuel removal, removal of<br />
nuclear processing fluids, post-operati<strong>on</strong>al clean out of fuel residues and removal of operati<strong>on</strong>al wastes. <str<strong>on</strong>g>The</str<strong>on</strong>g> work<br />
programme comprises activities in the following key areas: Policy, regulati<strong>on</strong> and strategy; Funding and costs;<br />
Techniques; Decommissi<strong>on</strong>ing materials management and site release; and Human and organisati<strong>on</strong>al factors. Recent<br />
trends in the above areas, as noted in a recent analysis by the WPDD, include: • Policy, regulati<strong>on</strong>s and strategy – most<br />
countries have adopted policies for decommissi<strong>on</strong>ing and for funding provisi<strong>on</strong>ing but a range of opti<strong>on</strong>s were being<br />
applied to the decommissi<strong>on</strong>ing of nuclear power plants (early dismantling, safe store and entombment), • Funding and<br />
costs – cost calculati<strong>on</strong>s for decommissi<strong>on</strong>ing are very sensitive to the assumed end-state and to the levels of<br />
c<strong>on</strong>taminati<strong>on</strong>s <strong>on</strong> the sites and may be greatly influenced by stakeholder requirements, • Techniques – the focus of<br />
current R&D is <strong>on</strong> the development of innovative technology for segmentati<strong>on</strong>, dismantling and c<strong>on</strong>crete<br />
dec<strong>on</strong>taminati<strong>on</strong>, together with better instrumentati<strong>on</strong> for material management and c<strong>on</strong>trol • Materials management and<br />
site release – there is a significant accelerati<strong>on</strong> in the number of decommissi<strong>on</strong>ing projects, including provisi<strong>on</strong> of<br />
infrastructure for storage of materials and for undertaking clearance and recycling of disused materials; • Human and<br />
organisati<strong>on</strong>al factors – efforts are being made to structure decommissi<strong>on</strong>ing c<strong>on</strong>tracts to optimise the supply chain<br />
relati<strong>on</strong>ships, with greater transparency and better communicati<strong>on</strong> am<strong>on</strong>gst all c<strong>on</strong>cerned parties; and • Stakeholder<br />
participati<strong>on</strong> and knowledge management – there is a range of approaches to stakeholder involvement in developing<br />
decommissi<strong>on</strong>ing plans and to rule making. In general, this issue is gaining momentum. A number of specific activities,<br />
projects and reports address the above areas. <str<strong>on</strong>g>The</str<strong>on</strong>g>y will be reviewed for the ICEM-2010 audience<br />
5) 40307 – French Decommissi<strong>on</strong>ing Feedback Experience and Less<strong>on</strong>s Learned<br />
Jean-Guy Nokhamz<strong>on</strong>, CEA (France); Patrick O'Sullivan, OECD/NEA<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> French (CEA, EDF and AREVA) experience in decommissi<strong>on</strong>ing of nuclear facilities goes back many decades<br />
and relates to many installati<strong>on</strong>s of very different types.<br />
Some twenty facilities were dealt with by 2009, corresp<strong>on</strong>ding to around half of all the nuclear facilities<br />
permanently closed up to date, beginning in March 2001 with the decommissi<strong>on</strong>ing of AT1 facility at La Hague, the pilot<br />
plant used by the CEA in the seventies for the reprocessing of spent fuel from fast neutr<strong>on</strong> reactors (former IAEA stage 3,<br />
excluding the civil engineering structures), as well as the blasting of G1 stack at Marcoule, <strong>on</strong> 19 July 2003 and ending<br />
with the total demoliti<strong>on</strong> of the research reactors Trit<strong>on</strong> and Néréide in F<strong>on</strong>tenay aux Roses in 2004 and the final steps<br />
for the total decommissi<strong>on</strong>ing of Siloë, Siloette and Mélusine in Grenoble research Centre by 2012.<br />
All the work d<strong>on</strong>e dem<strong>on</strong>strates the following:<br />
1) Decommissi<strong>on</strong>ing can and has been d<strong>on</strong>e in a safe, cost-effective and envir<strong>on</strong>mentally friendly manner.<br />
2) Current technologies have dem<strong>on</strong>strated their effectiveness and robust performance in numerous<br />
decommissi<strong>on</strong>ing activities. Feedback experience <strong>on</strong> design, c<strong>on</strong>structi<strong>on</strong> and operati<strong>on</strong> is a c<strong>on</strong>siderable help for<br />
reliable planning, cost evaluati<strong>on</strong> and successful realizati<strong>on</strong> of a decommissi<strong>on</strong>ing project.�<br />
3) During decommissi<strong>on</strong>ing radiological risks are very small in comparis<strong>on</strong> to n<strong>on</strong>-radiological risks.<br />
4) <str<strong>on</strong>g>The</str<strong>on</strong>g> disseminati<strong>on</strong> of best practices and sharing of informati<strong>on</strong> in internati<strong>on</strong>al workshops, c<strong>on</strong>ferences and<br />
especially within working groups as the OECD/NEA/CPD and IAEA/IDN has proven to be a good basis for an<br />
effective cooperati<strong>on</strong> and support to master new challenges <strong>on</strong> decommissi<strong>on</strong>ing projects.�<br />
5) Future challenges will require further internati<strong>on</strong>al cooperati<strong>on</strong> to establish sustainable regulati<strong>on</strong>s and<br />
guidance to achieve objectives without being burdensome or overly c<strong>on</strong>servative.<br />
6) A c<strong>on</strong>sistent, internati<strong>on</strong>ally accepted rati<strong>on</strong>ale is necessary for the elaborati<strong>on</strong> of c<strong>on</strong>cepts and for the<br />
derivati<strong>on</strong> of numerical values <strong>on</strong> clearance, exempti<strong>on</strong> and authorized releases.<br />
7) With decommissi<strong>on</strong>ing moving towards being a fully mature industrial process, increased dialogue am<strong>on</strong>g<br />
regulators, implementers and internati<strong>on</strong>al standards organisati<strong>on</strong>s is necessary.<br />
6) 40032 – Decommissi<strong>on</strong>ing Planning for Swedish Operating NPPs�<br />
Gunnar Hedin, Mathias Edelborg, Niklas Bergh, Westinghouse Electric Sweden (Sweden); Jan Carlss<strong>on</strong>, Fredrik<br />
de la Gardie, SKB (Sweden)<br />
47
Abstracts<br />
Decommissi<strong>on</strong>ing studies have been carried out for the three BWR units of Oskarshamn and the three BWR units of<br />
Forsmark nuclear power plants. <str<strong>on</strong>g>The</str<strong>on</strong>g> final closure of these units is far ahead but anyhow there has been a need for<br />
developing a more general decommissi<strong>on</strong>ing planning basis. <str<strong>on</strong>g>The</str<strong>on</strong>g> main objectives of the studies have been to establish an<br />
estimate of the waste amounts arising from these units during decommissi<strong>on</strong>ing and dismantling as well as providing a<br />
firm basis for funding of the decommissi<strong>on</strong>ing phase for these units. <str<strong>on</strong>g>The</str<strong>on</strong>g> waste amounts will be used when designing a<br />
separate repository for decommissi<strong>on</strong>ing waste of the same type as the existing facility for final disposal of short-lived<br />
low- and intermediate level waste, the SFR, at Forsmark, Sweden. <str<strong>on</strong>g>The</str<strong>on</strong>g> broader studies are also used for verificati<strong>on</strong> that<br />
the existing nati<strong>on</strong>al decommissi<strong>on</strong>ing fund is of an adequate size.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> studies have been performed by Westinghouse in cooperati<strong>on</strong> with the utilities of Forsmark (FKA) and<br />
Oskarshamn (OKG), <strong>on</strong> behalf of SKB, the utility-owned Swedish waste management organizati<strong>on</strong>, resp<strong>on</strong>sible for<br />
coordinati<strong>on</strong> of the nati<strong>on</strong>al waste fund as well as for designing, building and operati<strong>on</strong> of waste management facilities.<br />
Each of the studies c<strong>on</strong>tains a general descripti<strong>on</strong> of the plant with the purpose to characterize them to facilitate<br />
decommissi<strong>on</strong>ing project comparative studies of different plants. Also, a detailed inventory of all materials in the plant<br />
have been put together and modeling of radioactivity data have been carried out to establish typical c<strong>on</strong>taminati<strong>on</strong> levels<br />
for the main parts of the plant. <str<strong>on</strong>g>The</str<strong>on</strong>g> procedures and technologies foreseen to be used for the future dismantling and waste<br />
management work are briefly described based <strong>on</strong> standard, presently easily available techniques.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> combinati<strong>on</strong> of the materials inventory data and the radiological data is used to calculate the number of<br />
different waste c<strong>on</strong>tainers that will be produced during dismantling of the plant. Standard 20 feet ISO c<strong>on</strong>tainers will be<br />
used for the low-level waste while special steel c<strong>on</strong>tainers that fit the transport overpack system will be used for<br />
intermediate level waste. <str<strong>on</strong>g>The</str<strong>on</strong>g> l<strong>on</strong>g-lived waste will be loaded into thick-walled steel c<strong>on</strong>tainers.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> inventory data will also be used by experience models that calculate work hours for taking care of all the<br />
different types of plant comp<strong>on</strong>ents. <str<strong>on</strong>g>The</str<strong>on</strong>g> working time estimates are then combined, together with general durati<strong>on</strong> data<br />
for different activities during plant decommissi<strong>on</strong>ing, into a time schedule for the complete program, from initial<br />
planning and preparatory activities to n<strong>on</strong>-radioactive building demoliti<strong>on</strong> and site restorati<strong>on</strong>.<br />
Costs are then estimated for each of the work breakdown structure (WBS) elements of the time schedule.<br />
Summarized it provides a budgetary estimate for the complete decommissi<strong>on</strong>ing program. By rearranging the elements of<br />
the cost estimate according to the IAEA/EC/OECD-NEA comm<strong>on</strong> matrix (the “Yellow Book”), cost comparis<strong>on</strong> with<br />
other plants is facilitated.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper will provide detailed data of waste characterizati<strong>on</strong> and amounts, as well as of time schedules and cost<br />
estimates for the main part of the Swedish BWR fleet and show how decommissi<strong>on</strong>ing will fit with the existing<br />
well-developed waste management system of the country.<br />
7) 40104 – Chernobyl nuclear power plant Decommissi<strong>on</strong>ing Program<br />
Denys Tkachov, Dmytro Stelmakh, Viktor Kuchinskyy,<br />
State Special Enterprise Chernobyl Nuclear Power Plant (Ukraine)<br />
After terminati<strong>on</strong> of electricity generati<strong>on</strong> in December 2000, Chernobyl nuclear power plant (Ukraine) entered<br />
final shutdown stage that will be followed by decommissi<strong>on</strong>ing of the NPP units. Decommissi<strong>on</strong>ing activities will be<br />
performed <strong>on</strong> basis of the Decommissi<strong>on</strong>ing Program, developed at Chernobyl NPP in 2007. This document includes<br />
detailed descripti<strong>on</strong> and substantiati<strong>on</strong> of the selected decommissi<strong>on</strong>ing strategy, established sequence, durati<strong>on</strong> and<br />
basic c<strong>on</strong>tent of each decommissi<strong>on</strong>ing stage, as well as final state of the facility at the end of each stage. An informati<strong>on</strong><br />
required for using this document as guidance for decommissi<strong>on</strong>ing of Chernobyl NPP units is also comprised. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
Decommissi<strong>on</strong>ing Program of the Chernobyl NPP units is developed <strong>on</strong> basis of selected decommissi<strong>on</strong>ing strategy,<br />
namely<br />
– «deferred dismantling» (SAFESTOR), which includes follow stages: 1) Final shutdown and preservati<strong>on</strong> (10-12<br />
years); 2) Safe enclosure (up to 30 years); and 3) Dismantling (20 years). Chernobyl nuclear power plant is located in<br />
area, c<strong>on</strong>taminated by radioactive isotopes during the Accident at Unit 4 in 1986. In additi<strong>on</strong> Unit 3 has comm<strong>on</strong><br />
structures with Unit 4 (currently the “Shelter Object”). <str<strong>on</strong>g>The</str<strong>on</strong>g>se c<strong>on</strong>diti<strong>on</strong>s lead to the classificati<strong>on</strong> of the final state of the<br />
Chernobyl NPP site as “brown spot”. Major criteria of given state are limited release of materials and<br />
cleanup/dec<strong>on</strong>taminati<strong>on</strong> of the structures to the level of limited release from the regulatory c<strong>on</strong>trol. This article deals<br />
with issues <strong>on</strong> implementati<strong>on</strong> of decommissi<strong>on</strong>ing activities at Chernobyl NPP units, describe each decommissi<strong>on</strong>ing<br />
stage, its final state and main activities <strong>on</strong> each state. In additi<strong>on</strong> issues <strong>on</strong> the management of radioactive waste and<br />
spent nuclear fuel are included as well as basic Chernobyl NPP units decommissi<strong>on</strong>ing cost estimati<strong>on</strong>.<br />
8) 40273 – C<strong>on</strong>siderati<strong>on</strong>s for Grout Formulati<strong>on</strong>s in Facility Closures using In Situ Strategies<br />
John Gladen, Mike Serrato, Chris Langt<strong>on</strong>, Savannah River Nati<strong>on</strong>al Laboratory (USA);<br />
Andy Szilagyi, US DOE (USA)�<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> U.S. Department of Energy is c<strong>on</strong>ducting In Situ closures (entombment) at a large number of facilities<br />
throughout the complex. Am<strong>on</strong>g the largest closure acti<strong>on</strong>s currently underway is the closure of the P and R Reactors at<br />
the Savannah River Site. Below grade open spaces in these facilities are being stabilized with grout to ensure the l<strong>on</strong>g<br />
term structural integrity of the facility which ensures the permanent immobilizati<strong>on</strong> of residual c<strong>on</strong>taminati<strong>on</strong>.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> large size and structural complexity of these facilities present a wide variety of challenges for the identificati<strong>on</strong><br />
and selecti<strong>on</strong> of appropriate fill materials. C<strong>on</strong>siderati<strong>on</strong>s for grout formulati<strong>on</strong>s must account for flowability, l<strong>on</strong>g term<br />
48
Abstracts<br />
stability, set times, heat generati<strong>on</strong> and interacti<strong>on</strong>s with materials within the structure. <str<strong>on</strong>g>The</str<strong>on</strong>g> large size and c<strong>on</strong>figurati<strong>on</strong><br />
of the facility necessitates that grout must be pumped from the exterior to the spaces to be filled, which requires that the<br />
material must retain a high degree of flowability to move through piping without clogging while achieving the required<br />
leveling properties at the pour site. Set times and curing properties must be c<strong>on</strong>trolled to meet operati<strong>on</strong>s schedules,<br />
while not generating sufficient heat to compromise the properties of the fill material.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> properties of residual materials can result in additi<strong>on</strong>al requirements for grout formulati<strong>on</strong>s. If significant<br />
quantities of aluminum are present in the facility, comm<strong>on</strong> formulati<strong>on</strong>s of highly alkaline grouts may not be appropriate<br />
because of the potential for hydrogen generati<strong>on</strong> with the resultant risks. <str<strong>on</strong>g>The</str<strong>on</strong>g> SRS is developing specialized inorganic<br />
grout formulati<strong>on</strong>s that are designed to address this potential problem. One circum-neutral chemical grout formulati<strong>on</strong><br />
identified for initial c<strong>on</strong>siderati<strong>on</strong> did not possess the proper chemical characteristics having excepti<strong>on</strong>ally short set times<br />
and high heat of hydrati<strong>on</strong>. Research efforts are directed toward developing formulati<strong>on</strong>s that can meet operati<strong>on</strong>al<br />
requirements for chemical compatibility, extended set times and reduced heat generati<strong>on</strong>.<br />
SESSION R1: Envir<strong>on</strong>mental Impacts<br />
1) 40298 – Main Results of A Remediati<strong>on</strong> of Uranium- and CHC-C<strong>on</strong>taminated Groundwater<br />
Jörg Wörner, S<strong>on</strong>ja Margraf, Walter Hackel, RD-Hanau (Germany)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> ground-water of a former research- and producti<strong>on</strong> site for various nuclear fuel-elements has been remediated<br />
for the last 8 years taking place after an intensive soilremediati<strong>on</strong> by large-scale drilling and additi<strong>on</strong>al soil-exchange<br />
within the saturated z<strong>on</strong>e. <str<strong>on</strong>g>The</str<strong>on</strong>g> remediati<strong>on</strong>-activities were improved successfully by several measures of which <strong>on</strong>e was<br />
the increase of the plant’s throughput and another the setting of additi<strong>on</strong>al remediati<strong>on</strong>-wells at selected places. This<br />
procedure is mainly based <strong>on</strong> the regular observati<strong>on</strong> of the remaining c<strong>on</strong>taminants’ c<strong>on</strong>centrati<strong>on</strong>s in the ground-water<br />
and the aquifer’s specific lithography. <str<strong>on</strong>g>The</str<strong>on</strong>g> cleaning process was adopted for a sec<strong>on</strong>d installati<strong>on</strong> which was taken in<br />
operati<strong>on</strong> last November. Both installati<strong>on</strong>s’ experience will be presented by which about 450.000 m³ ground-water will<br />
have been extracted by midyear. <str<strong>on</strong>g>The</str<strong>on</strong>g> area affected by the c<strong>on</strong>taminants has been downsized by the remediati<strong>on</strong> which is<br />
manifested by the results of the m<strong>on</strong>thly m<strong>on</strong>itoring. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>venti<strong>on</strong>ally set target-values have not yet been reached, but<br />
the progress will offer the chance to release the remediati<strong>on</strong> out of the rules of the German Atomic Law by the year 2013.<br />
Details in the ground-water’s Uranium-nuclide compositi<strong>on</strong> allow the attributi<strong>on</strong> of the ground-water to two main plumes<br />
associated to different former producti<strong>on</strong>-activities. Blending of the two plumes with respect to their specific<br />
Uranium-nuclide compositi<strong>on</strong> caused by the chosen pump-regime has been observed and is meanwhile a helpful means<br />
for reaching the set aims <strong>on</strong> a planned time-scale. Figures for the totally extracted amounts of Uranium and CHC<br />
(chlorinated hydrocarb<strong>on</strong>s) will be presented which are increasing actually for both c<strong>on</strong>taminants as result of setting<br />
additi<strong>on</strong>al remediati<strong>on</strong>-wells close to the still- observable c<strong>on</strong>taminati<strong>on</strong>-centres. Completely remediated areas are<br />
observed <strong>on</strong> the other hand where intensive pumping was executed from the very beginning of the remediati<strong>on</strong>-activities.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se observati<strong>on</strong>s give data to estimate the residual amounts of ground-water which have to be treated in the future. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
decrease of the Uranium-c<strong>on</strong>taminati<strong>on</strong> is observed as a functi<strong>on</strong> of the extracted amount of ground-water whereas the<br />
CHC-c<strong>on</strong>taminati<strong>on</strong> has decreased irregularly due to the fact of its dependence of the pump-regime and the<br />
remediati<strong>on</strong>-wells’ different distances to the former handling locati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> CHC-compound-spectrum shows natural<br />
attenuati<strong>on</strong> effects in the close down-stream area which can be helpful after achievement of the remediati<strong>on</strong>’s<br />
target-value for the Uranium and possible finalizing of a c<strong>on</strong>tinuous pumping procedure. As detailed results were<br />
published in two former ICEM-papers [1,2] this paper will highlight main results and discuss taken measures to finalize<br />
the remediati<strong>on</strong>-activities within the next 3 to 4 years. [1] ICEM07-7270 Remediati<strong>on</strong> of a Uranium-c<strong>on</strong>taminati<strong>on</strong> in<br />
groundwater, [2] ICEM09-16244 Remediati<strong>on</strong> of Uranium- and CHC-c<strong>on</strong>taminated groundwater <strong>on</strong> a former nuclear<br />
fuel-element producti<strong>on</strong> site.<br />
2) 40267 – Biogeochemical Gradients, Waste Site Evoluti<strong>on</strong>, and Implicati<strong>on</strong>s for Sustained Metal and<br />
Radi<strong>on</strong>uclide Attenuati<strong>on</strong> in Complex Subsurface Envir<strong>on</strong>ments<br />
Karen Skulbal, Justin Marble, Kurt D. Gerdes, US DOE (USA);<br />
Miles Denham, Karen Vangelas, Savannah River Nati<strong>on</strong>al Laboratory (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> U.S. Department of Energy (DOE) Office of Technology Innovati<strong>on</strong> and Development sp<strong>on</strong>sors applied<br />
research to improve the understanding of metal and radi<strong>on</strong>uclide behavior in soil, sediment, and groundwater.<br />
DOE-supported researchers are developing advanced site characterizati<strong>on</strong> and simulati<strong>on</strong> capabilities, as well as novel<br />
remediati<strong>on</strong> tools and technologies to c<strong>on</strong>trol c<strong>on</strong>taminants over l<strong>on</strong>g time frames in highly complex subsurface<br />
envir<strong>on</strong>ments. Natural and enhanced attenuati<strong>on</strong> strategies are being studied in the c<strong>on</strong>text of subsurface biogeochemical<br />
gradients, such as variati<strong>on</strong>s in pH and redox potential. <str<strong>on</strong>g>The</str<strong>on</strong>g>se gradients are spatially and temporally dynamic and can<br />
str<strong>on</strong>gly influence metal and radi<strong>on</strong>uclide migrati<strong>on</strong>, speciati<strong>on</strong>, and reactivity. Knowledge of gradient evoluti<strong>on</strong> is<br />
essential for site evaluati<strong>on</strong>, initial remedy selecti<strong>on</strong>, and technology transiti<strong>on</strong>ing to sustainable, low-energy remediati<strong>on</strong><br />
approaches such as m<strong>on</strong>itored natural attenuati<strong>on</strong>. Research activities in this area will be discussed using case studies<br />
from DOE sites. One case study focuses <strong>on</strong> a former disposal area at the Savannah River Site (SRS) in Aiken, South<br />
Carolina. Unlined seepage basins at the site received approximately seven billi<strong>on</strong> liters of acidic, aqueous, low-level<br />
49
Abstracts<br />
radioactive waste over more than three decades. <str<strong>on</strong>g>The</str<strong>on</strong>g> resulting groundwater plume c<strong>on</strong>tains multiple c<strong>on</strong>taminants,<br />
including nitrate, iodine-129, str<strong>on</strong>tium-90, technetium-99, tritium, and uranium isotopes. Since 1991, groundwater near<br />
the source area has been analyzed for evidence that plume acidity is naturally attenuating. Other biogeochemical<br />
gradients are also being evaluated to determine natural waste site evoluti<strong>on</strong> and impacts from active remediati<strong>on</strong> systems.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se systems include a neutralizati<strong>on</strong> barrier to mitigate plume acidity and a biostimulati<strong>on</strong> z<strong>on</strong>e to enhance in situ<br />
reductive metal precipitati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> influence of reactive facies <strong>on</strong> plume dynamics is also being examined using<br />
geophysical tools to detect these subsurface z<strong>on</strong>es of unique mineralogy, hydrology, and microbiology. Site<br />
characterizati<strong>on</strong> data, plume dynamics, and c<strong>on</strong>taminant behavior are incorporated into an evolving site c<strong>on</strong>ceptual model,<br />
which serves as the foundati<strong>on</strong> for reactive transport modeling. This unique approach for site assessment is expected to<br />
improve the selecti<strong>on</strong> of remedial strategies and decisi<strong>on</strong> making for l<strong>on</strong>g-term envir<strong>on</strong>mental stewardship at SRS and<br />
other sites. <str<strong>on</strong>g>The</str<strong>on</strong>g> work is complementary to the U.S. Envir<strong>on</strong>mental Protecti<strong>on</strong> Agency’s recent guidance <strong>on</strong> m<strong>on</strong>itored<br />
natural attenuati<strong>on</strong> of inorganics.<br />
3) 40260 – Current Mercury Distributi<strong>on</strong> and Bioavailability in Floodplain Soils of Lower East Fork Popular<br />
Creek, Oak Ridge, Tennessee, USA<br />
Fengxiang X. Han, Yi Su, David L. M<strong>on</strong>ts,� Mississippi State University (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> objectives of this study were to investigate the current status of mercury distributi<strong>on</strong>, speciati<strong>on</strong> and<br />
bioavailability in the floodplain soils of Lower East Fork Poplar Creek (LEFPC) after decades of US Department of<br />
Energy’s remediati<strong>on</strong>. Historically as part of its nati<strong>on</strong>al security missi<strong>on</strong>, the U.S. Department of Energy’s Y-12<br />
Nati<strong>on</strong>al Security Facility in Oak Ridge, TN, USA acquired a significant fracti<strong>on</strong> of the world’s supply of elemental<br />
mercury. During the 1950s and 1960s, a large amount of elemental mercury escaped c<strong>on</strong>finement and is still present in<br />
the watershed surrounding the Y-12 facility. A series of remediati<strong>on</strong> efforts have been deployed in the watersheds around<br />
the Oak Ridge site during the following years. <str<strong>on</strong>g>The</str<strong>on</strong>g> sampling fields were located in a floodplain of LEFPC of Oak Ridge,<br />
TN, USA. A series of surface soils (10-20 cm) were sampled from both wooded areas and wetland/grass land. Two 8x8<br />
m fields were selected in the woodland. Five profiles each c<strong>on</strong>sisting of three layers were randomly taken from each field.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> three layers were the surface layer at 0-10cm, subsurface layer at 50-60 cm, and bottom layer at 100-110 cm. Soil in<br />
both wood and wetland areas was well developed with a clear B horiz<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> present study clearly shows that the total<br />
mercury in floodplain soils of LEFPC significantly decreased after the series of remediati<strong>on</strong>. This study c<strong>on</strong>firmed the<br />
l<strong>on</strong>g-term effectiveness of these remediati<strong>on</strong> acti<strong>on</strong>s, especially after excavati<strong>on</strong> of highly c<strong>on</strong>taminated floodplain soils.<br />
However, the average total mercury level of all soil samples collected are in the range of 50-80 mg/kg, still significantly<br />
above toxic level (> 5mg/kg). Furthermore, c<strong>on</strong>trary to c<strong>on</strong>venti<strong>on</strong>al believing, the major mercury form in current soils of<br />
this particular area of floodplain of LEFPC is mainly in n<strong>on</strong>-cinnabar mercury bound in clay minerals (after decades of<br />
remediati<strong>on</strong>). <str<strong>on</strong>g>The</str<strong>on</strong>g> floodplains can act both as a medium-term sink and as l<strong>on</strong>g-term sources. Native North American<br />
earthworms (Diplocardia spp.) and adjacent soils were taken from each spot in each field. Our results show str<strong>on</strong>g linear<br />
relati<strong>on</strong>ships between mercury c<strong>on</strong>centrati<strong>on</strong>s in earthworms (both mature and immature groups) and n<strong>on</strong>-cinnabar<br />
mercury form, while cinnabar mercury is less bioavailable to native earthworms. Earthworms may be used as a potential<br />
mercury ecological bioindicator (bio-marker) for dem<strong>on</strong>strating mercury bioavailability and ecotoxicity in the ecosystem.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> l<strong>on</strong>g-term stability, mobility and bioavailability of mercury c<strong>on</strong>taminants in these floodplains still needs to be<br />
m<strong>on</strong>itored c<strong>on</strong>tinuously and closely.<br />
4) 40262 – Integrated Strategy to Address Hanford's Deep Vadose Z<strong>on</strong>e Remediati<strong>on</strong> Challenges<br />
Mark B. Triplett, Mark D. Freshley, Michael J. Truex, Dawn Wellman, PNNL (USA);<br />
Kurt D. Gerdes, Briant L. Charb<strong>on</strong>eau, John G. Morse, Robert W. Lober, US DOE (USA);<br />
Glen B. Chr<strong>on</strong>ister, CH2M Hill Plateau Remediati<strong>on</strong> Company (USA)<br />
A vast majority of Hanford’s remaining in-ground c<strong>on</strong>taminants reside in the vadose z<strong>on</strong>e of the 200 Area Central<br />
Plateau, where reprocessing operati<strong>on</strong>s occurred. <str<strong>on</strong>g>The</str<strong>on</strong>g> vadose z<strong>on</strong>e at this locati<strong>on</strong> is comprised of about 75 meters of<br />
water-unsaturated, unc<strong>on</strong>solidated, stratified sediments above groundwater that discharges to the Columbia River.<br />
C<strong>on</strong>taminants in this z<strong>on</strong>e originated from intenti<strong>on</strong>al discharges to cribs, retenti<strong>on</strong> basins, and trenches, and from<br />
unintended tank waste releases in the tank farms. <str<strong>on</strong>g>The</str<strong>on</strong>g> “deep vadose z<strong>on</strong>e” is defined as the regi<strong>on</strong> below the practical<br />
depth of surface remedy influence (e.g., excavati<strong>on</strong> or surface barrier). At the Hanford Site, this regi<strong>on</strong> poses unique<br />
challenges for characterizati<strong>on</strong> and remediati<strong>on</strong>.<br />
In 2008, the Department of Energy initiated a deep vadose z<strong>on</strong>e treatability test to seek remedies for technetium-99<br />
and uranium c<strong>on</strong>taminati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> treatability approach includes laboratory, modeling, and field tests building <strong>on</strong> previous<br />
work at the Hanford Site. Initial laboratory and field tests for technetium-99 have focused <strong>on</strong> use of desiccati<strong>on</strong> which<br />
could be used in combinati<strong>on</strong> with an infiltrati<strong>on</strong> barrier to slow the transport of technetium-99 in the subsurface. For<br />
uranium c<strong>on</strong>taminati<strong>on</strong>, reactive gas technologies are being tested as <strong>on</strong>e comp<strong>on</strong>ent of the overall treatability test<br />
approach.<br />
More recently, in recogniti<strong>on</strong> of the need for a broader strategy, the Department of Energy initiated an integrated<br />
study of the deep vadose z<strong>on</strong>e to establish a technical basis for addressing risk-driving c<strong>on</strong>taminants and supporting<br />
selecti<strong>on</strong> of remediati<strong>on</strong> approaches for the deep vadose z<strong>on</strong>e that are protective of groundwater. This is a cooperative<br />
effort that combines the resources and c<strong>on</strong>tributi<strong>on</strong>s of research scientists, technology developers, and remediati<strong>on</strong><br />
c<strong>on</strong>tractors.<br />
50
Abstracts<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> objectives of the deep vadose z<strong>on</strong>e strategy are to:<br />
• Develop sufficient understanding of the nature and extent of deep vadose z<strong>on</strong>e c<strong>on</strong>taminati<strong>on</strong> and processes that<br />
affect fate and transport;<br />
• Develop predictive capabilities for describing c<strong>on</strong>taminant fate and transport as well as flux from the vadose<br />
z<strong>on</strong>e to the groundwater;<br />
• Develop, test and deploy effective methods for remediating c<strong>on</strong>taminated areas;<br />
• Develop and deploy effective m<strong>on</strong>itoring methods for assessing the performance of remedies and for<br />
determining the l<strong>on</strong>g-term threat of c<strong>on</strong>taminants to the groundwater.<br />
5) 40235 – Advanced Remedial Methods for Metals and Radi<strong>on</strong>uclides in Deep Vadose Z<strong>on</strong>e Envir<strong>on</strong>ments<br />
Dawn Wellman, Shas Mattigod, Ann Miracle, Lir<strong>on</strong>g Zh<strong>on</strong>g, Danielle Jansik, PNNL (USA);<br />
Susan Hubbard, Yuxin Wu, LBNL (USA); Martin Foote, MSE (USA)<br />
Deep vadose z<strong>on</strong>e envir<strong>on</strong>ments can be a primary source and pathway for c<strong>on</strong>taminant migrati<strong>on</strong> to groundwater.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se envir<strong>on</strong>ments present unique characterizati<strong>on</strong> and remediati<strong>on</strong> challenges that necessitate scrutiny and research.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> thickness, depth, and intricacies of the deep vadose z<strong>on</strong>e, combined with a lack of understanding of the key<br />
subsurface processes (e.g., biogeochemical and hydrologic) affecting c<strong>on</strong>taminant migrati<strong>on</strong>, make it difficult to create<br />
validated c<strong>on</strong>ceptual and predictive models of subsurface flow dynamics and c<strong>on</strong>taminant behavior across multiple scales.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se factors also make it difficult to design and deploy sustainable remedial approaches and m<strong>on</strong>itor l<strong>on</strong>g-term<br />
c<strong>on</strong>taminant behavior after remedial acti<strong>on</strong>s.<br />
Functi<strong>on</strong>ally, the methods for addressing c<strong>on</strong>taminati<strong>on</strong> must remove and/or reduce transport of c<strong>on</strong>taminants. This<br />
problem is particularly challenging in the arid western USA where the vadose z<strong>on</strong>e is hundreds of feet thick, rendering<br />
transiti<strong>on</strong>al excavati<strong>on</strong> methods exceedingly costly and ineffective. Delivery of remedial amendments is <strong>on</strong>e of the most<br />
challenging and critical aspects for all remedy-based approaches. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>venti<strong>on</strong>al approach for delivery is through<br />
injecti<strong>on</strong> of aqueous remedial soluti<strong>on</strong>s. However, heterogeneous deep vadose z<strong>on</strong>e envir<strong>on</strong>ments present hydrologic and<br />
geochemical challenges which limit the effectiveness. Because the flow of soluti<strong>on</strong> infiltrati<strong>on</strong> is dominantly c<strong>on</strong>trolled<br />
by gravity and sucti<strong>on</strong>, injected liquid preferentially percolates through highly permeable pathways, by-passing<br />
low-permeability z<strong>on</strong>es which frequently c<strong>on</strong>tain the majority of c<strong>on</strong>taminati<strong>on</strong>. Moreover, the wetting fr<strong>on</strong>t can readily<br />
mobilize and enhance c<strong>on</strong>taminant transport to the underlying aquifer prior to stabilizati<strong>on</strong>. Development of innovative,<br />
in-situ technologies may be the <strong>on</strong>ly way to meet remedial acti<strong>on</strong> objectives and l<strong>on</strong>g-term stewardship goals.<br />
Shear-thinning fluids (i.e., surfactants) can be used to lower the liquid surface tensi<strong>on</strong> and create stabile foams,<br />
which readily penetrate low permeability z<strong>on</strong>es. Although surfactant foams have been utilized for subsurface<br />
mobilizati<strong>on</strong> efforts in the oil and gas industry, so far, the c<strong>on</strong>cept of using foams as a delivery mechanism for<br />
transporting remedial amendments into deep vadose z<strong>on</strong>e envir<strong>on</strong>ments to stabilize metal and l<strong>on</strong>g-lived radi<strong>on</strong>uclide<br />
c<strong>on</strong>taminants has not been explored. Foam flow can be directed by pressure gradients, rather than being dominated by<br />
gravity; and, foam delivery mechanisms limit the volume of water (< 5% vol.) required for remedy delivery and<br />
emplacement, thus mitigating c<strong>on</strong>taminant mobilizati<strong>on</strong>. We will present the results of a numerical modeling and<br />
integrated laboratory- / intermediate-scale investigati<strong>on</strong> to simulate, develop, dem<strong>on</strong>strate, and m<strong>on</strong>itor (i.e. advanced<br />
geophysical techniques and advanced predictive biomarkers) foam-based delivery of remedial amendments to remediate<br />
metals and radi<strong>on</strong>uclides in vadose z<strong>on</strong>e envir<strong>on</strong>ments.<br />
6) 40152 Water discharge from the Chernobyl NPP cooling p<strong>on</strong>d: the main challenges of the envir<strong>on</strong>mental<br />
protecti<strong>on</strong> during post-rehabilitati<strong>on</strong> period<br />
Dmitri Gudkov, Institute of Hydrobiology (Ukraine)<br />
One of the problems c<strong>on</strong>nected with decommissi<strong>on</strong>ing of the Chernobyl NPP is further destiny of the cooling p<strong>on</strong>d<br />
and planned in 2010 a water discharge from it. Cooling p<strong>on</strong>ds was created <strong>on</strong> the floodplain part of the Pripyat River<br />
(main tributary of the Dnieper River) and exhibits an oval in 11-km length and about 2-km width. Pumping of water from<br />
the Pripyat River provides the c<strong>on</strong>stant level of water. In 1986 during Chernobyl NPP accident the huge quantity of<br />
radi<strong>on</strong>uclides has dropped out directly <strong>on</strong> a water surface, and also was released with reactor waters and has appeared in<br />
the cooling p<strong>on</strong>d. Now in the bottom sediments of the cooling p<strong>on</strong>d deposited about (16±3)E+13 Bq of Cs-137,<br />
(2,4±0,9)E+13 Bq of Sr-90 and (5,3±1,9)E+11 Bq of Pu-239+240. More than 30-50 % of the total radi<strong>on</strong>uclide activity<br />
deposited in the bottom sediments <strong>on</strong> the depths less than 7 m. After cessati<strong>on</strong> of pump stati<strong>on</strong> during 5-6 years<br />
(depending <strong>on</strong> c<strong>on</strong>crete natural c<strong>on</strong>diti<strong>on</strong>s) the level of water will decrease <strong>on</strong> 6-7 m to a level of the Pripyat River and<br />
<strong>on</strong> a site of the cooling p<strong>on</strong>d al<strong>on</strong>g old river-bed there will be a chain of floodplain lakes It is supposed that water drain<br />
into the Dnieper River system will not result to any radiological c<strong>on</strong>sequences for the envir<strong>on</strong>ment and human health.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> basic c<strong>on</strong>tingent, working in the exclusi<strong>on</strong> z<strong>on</strong>e, will not be subject to influence of carry of radioactive dust from<br />
surface of the drained sites of the cooling p<strong>on</strong>d, and the c<strong>on</strong>tributi<strong>on</strong> of inhalati<strong>on</strong> doze of irradiati<strong>on</strong> will be not essential<br />
in comparis<strong>on</strong> with impact of other sources of c<strong>on</strong>taminati<strong>on</strong>. At the same time for the pers<strong>on</strong>nel that will be involved in<br />
rehabilitati<strong>on</strong> work within the drained area of bottom, the inhalati<strong>on</strong> doze of irradiati<strong>on</strong> can be essential. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore the<br />
measure <strong>on</strong> dust depressing will be desirable until the steady obliterati<strong>on</strong> of the open sites of the p<strong>on</strong>d bottom by<br />
vegetati<strong>on</strong> will take place. At that the phyto-rehabilitati<strong>on</strong> measures, allowing to speed up an obliterati<strong>on</strong> of drained most<br />
c<strong>on</strong>taminated sites of bottom surface with oozy sediments and being a source of radioactive aerosols eolomoti<strong>on</strong> can be<br />
51
Abstracts<br />
effectual. Unfortunately, am<strong>on</strong>g expected problems at the water drain in the cooling p<strong>on</strong>d the most complicated <strong>on</strong>e can<br />
appear not solved problem of safe recycling or natural transformati<strong>on</strong> of higher aquatic plants, phyto- and zooplankt<strong>on</strong>,<br />
molluscs and fish. <str<strong>on</strong>g>The</str<strong>on</strong>g> planned mode of water drain will result in destructi<strong>on</strong> of huge both <strong>on</strong> biomass and quantity of<br />
plant and animal species. Up to 100,000 t<strong>on</strong>s of biota, am<strong>on</strong>g which practically all of higher aquatic plants, zoobenthos,<br />
significant quantity of fish, will be lost. Many species of waterfowls and other birds will lose their habitats, including rare,<br />
vulnerable and endangered species. Separately it is necessary to menti<strong>on</strong> the problem of dose rate increase <strong>on</strong> biota due<br />
to occupancy of drained territories with high density of radioactive c<strong>on</strong>taminati<strong>on</strong>, and also in c<strong>on</strong>necti<strong>on</strong> with expected<br />
increase of the radi<strong>on</strong>uclide c<strong>on</strong>tent in all comp<strong>on</strong>ents of lake ecosystems, which will formed after water drain of the<br />
cooling p<strong>on</strong>d.<br />
SESSION M1: Envir<strong>on</strong>mental Management<br />
1) 40086 – Legacy Management: Turning Liabilities into Assets<br />
Joe Legare, Eric Ols<strong>on</strong>, S.M. Stoller Corporati<strong>on</strong> (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> U.S. Department of Energy (DOE) Office of Legacy Management (LM) is resp<strong>on</strong>sible for stewardship of over<br />
85 sites across the USA dating back to the Manhattan Project and associated with the nuclear weap<strong>on</strong>s producti<strong>on</strong><br />
missi<strong>on</strong>. This resp<strong>on</strong>sibility for the l<strong>on</strong>g-term envir<strong>on</strong>mental management of these sites includes the key requirements to<br />
ensure protecti<strong>on</strong> of human health and protecti<strong>on</strong> of the envir<strong>on</strong>ment from residual c<strong>on</strong>taminati<strong>on</strong>, and to manage over<br />
100,000 ft3 of associated records.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Legacy Management program, through its prime c<strong>on</strong>tractor, provides program management, field and technical<br />
support, data collecti<strong>on</strong> and analysis and project planning and implementati<strong>on</strong> in support of the DOE to achieve its<br />
missi<strong>on</strong>. With a defined program baseline of 75 years, and a theoretical baseline that may extend bey<strong>on</strong>d this time period,<br />
effective programmatic integrati<strong>on</strong> of these myriad sites, and appropriate c<strong>on</strong>siderati<strong>on</strong> of life-cycle implicati<strong>on</strong>s to risk<br />
and cost of stewardship decisi<strong>on</strong>s is essential to the success of the program.<br />
This presentati<strong>on</strong> will provide an overview of the more than 85 sites in the Legacy Management program, including<br />
a discussi<strong>on</strong> of prior missi<strong>on</strong> and associated envir<strong>on</strong>mental c<strong>on</strong>taminati<strong>on</strong> issues; ramificati<strong>on</strong>s of the different regulatory<br />
and cleanup approaches taken during active remediati<strong>on</strong>; and the challenges of the current l<strong>on</strong>g-term surveillance and<br />
maintenance missi<strong>on</strong>. Additi<strong>on</strong>ally, the presentati<strong>on</strong> will address less<strong>on</strong>s learned during the first eight years of the<br />
Legacy Management program in terms of risk management, public and stakeholder involvement, instituti<strong>on</strong>al c<strong>on</strong>trols,<br />
regulatory agreements and the issues associated with transiti<strong>on</strong> from active remediati<strong>on</strong> to l<strong>on</strong>g-term surveillance and<br />
maintenance. Some of the case histories of how envir<strong>on</strong>mental management of these varied sites has evolved over time<br />
will be presented.<br />
2) 40270 – Less<strong>on</strong>s Learned in Planning the Canadian Nuclear Legacy Liabilities Program<br />
Michael Stephens, Sheila M. Brooks, Joan Miller, Robert Mas<strong>on</strong>, AECL (Canada)<br />
In 2006, AECL and Natural Resources Canada (NRCan) began implementing a Nuclear Legacy Liabilities Program<br />
(NLLP) to manage the liabilities at AECL’s nuclear sites in Canada. <str<strong>on</strong>g>The</str<strong>on</strong>g>se liabilities include shutdown research and<br />
prototype power reactors, fuel-handling facilities, radiochemical laboratories, support buildings, radioactive waste<br />
storage facilities, and c<strong>on</strong>taminated lands. <str<strong>on</strong>g>The</str<strong>on</strong>g> delivery of the Program is managed by a Liability Management Unit<br />
(LMU) within AECL.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> NLLP comprises a large program of interlinked decommissi<strong>on</strong>ing, waste management and envir<strong>on</strong>mental<br />
restorati<strong>on</strong> activities being executed at different sites, and by various technical groups as suppliers to the LMU. This<br />
paper describes the less<strong>on</strong>s learned in planning the “start-up” phase, which will c<strong>on</strong>clude 2011 March, and the planning<br />
of the sec<strong>on</strong>d phase, a 5-year program, which is currently being finalized.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> initial “start-up” phase was planned by a small group of experts. Although effort was made to communicate the<br />
goals and overall strategy of the Program to the groups that would carry out the work, progress was slower than<br />
anticipated because AECL was ramping up from a minimal maintenance mode and the required increase in staff and<br />
technical resources was not sufficiently understood. Many of the projects being addressed within the Program are <strong>on</strong>eof-a-kind,<br />
and the essential base informati<strong>on</strong> <strong>on</strong> which to prepare detailed executi<strong>on</strong> plans was not available to accurately<br />
plan the work.<br />
Internal reviews of the Program examined progress and identified several improvements to planning. <str<strong>on</strong>g>The</str<strong>on</strong>g>se<br />
included strengthening communicati<strong>on</strong>s, c<strong>on</strong>ducting more advance planning of the interlinked activities, and building<br />
flexibility into the commitments made about activities that had yet to reach major decisi<strong>on</strong> points.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> priorities for executing the required activities in the Program were set using criteria based <strong>on</strong> risks the liabilities<br />
presented to health, safety, the envir<strong>on</strong>ment and to AECL’s business. In future, the decisi<strong>on</strong> criteria will also include the<br />
value gained for funds expended, and greater c<strong>on</strong>siderati<strong>on</strong> will be given to mitigating risks to the executi<strong>on</strong> of the<br />
Program. It was also determined that licensing strategies and processes need to be well-defined, and waste<br />
characterizati<strong>on</strong> methods and dispositi<strong>on</strong> pathways must be in place to deal with the wastes the Program will generate.<br />
Case studies will be presented in the paper to illustrate these less<strong>on</strong>s learned.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> NLLP is funded by the Government of Canada through NRCan.<br />
52
Abstracts<br />
3) 40292 – GIS-Based Decisi<strong>on</strong> Support System for the Former Semipalatinsk Test Site<br />
Maira Mukusheva, Sergey Baranov, Nati<strong>on</strong>al Nuclear Center (Kazakhstan)<br />
Terminati<strong>on</strong> of the nuclear tests and closure of the Semipalatinsk test site, taking into account the collapsed<br />
ec<strong>on</strong>omy of the former Soviet Uni<strong>on</strong> brought to a situati<strong>on</strong> when a huge area most part of which was c<strong>on</strong>taminated with<br />
radioactive substances became open and unc<strong>on</strong>trolled providing a free access to the test site. Residents from the<br />
neighboring settlements used the opportunity. <str<strong>on</strong>g>The</str<strong>on</strong>g>y did not realize the hazard imposed during live-stock grazing, ferrous<br />
and n<strong>on</strong>-ferrous metal scavenging, dismantling of buildings and structures located at the area. Grazing areas of some<br />
wintering grounds are located close to the nuclear tests areas. People living at the wintering ground and summer pastures,<br />
are occupied with grazing of cattle, sheep stock and drove of horses. Radioactive c<strong>on</strong>taminati<strong>on</strong> of the site is caused by<br />
ground and above-ground nuclear explosi<strong>on</strong>s. In such a situati<strong>on</strong> the main task was evaluati<strong>on</strong> and predicti<strong>on</strong> of<br />
radioecological situati<strong>on</strong>, safety of ec<strong>on</strong>omic activity. Applicati<strong>on</strong> of geographic informati<strong>on</strong>al systems for analysis of<br />
radioecological process at radioactive c<strong>on</strong>taminated nuclear test locati<strong>on</strong>s will make possible to process large amount of<br />
different informati<strong>on</strong> required for soluti<strong>on</strong> of problems related to the rehabilitati<strong>on</strong> of c<strong>on</strong>taminated areas. Efficiency,<br />
possibility to integrate ecological, social, ec<strong>on</strong>omic, and management informati<strong>on</strong> <strong>on</strong> the unified geographic basis and<br />
combinati<strong>on</strong> with mathematic analysis tools, distinguish the geoinformati<strong>on</strong>al systems out of the existing applied<br />
programs. <str<strong>on</strong>g>The</str<strong>on</strong>g> universality determines the attractiveness of their applicati<strong>on</strong> for a wide range of tasks. To evaluate and<br />
predict radioecological situati<strong>on</strong> at the STS, a radioecological m<strong>on</strong>itoring system (REMS) is developed <strong>on</strong> the basis of<br />
GIS-technologies. <str<strong>on</strong>g>The</str<strong>on</strong>g> system is designed to provide informati<strong>on</strong>, methodic and instrument support for preparati<strong>on</strong><br />
processes and management decisi<strong>on</strong> making in ec<strong>on</strong>omic activity at the STS. To check the efficiency of the REMS and<br />
dem<strong>on</strong>strate applicability of GIS-technologies, risks calculati<strong>on</strong> is performed for the STS populati<strong>on</strong> as part of analysis<br />
for c<strong>on</strong>sequences of ecosystems radioactive c<strong>on</strong>taminati<strong>on</strong>. On the basis of analysis for references, field and laboratory<br />
experiments, main ways of pasture ecosystems c<strong>on</strong>taminati<strong>on</strong> at STS are revealed and radi<strong>on</strong>uclides are determined<br />
which make the most c<strong>on</strong>tributi<strong>on</strong> to the additi<strong>on</strong>al radiati<strong>on</strong> exposure to populati<strong>on</strong> carrying <strong>on</strong> ec<strong>on</strong>omic activity in the<br />
regi<strong>on</strong>. Revised is the nature of agricultural producti<strong>on</strong>, schematic maps are c<strong>on</strong>structed for locati<strong>on</strong> of ec<strong>on</strong>omic agents.<br />
Using all available informati<strong>on</strong>, evaluati<strong>on</strong> is carried out for actual c<strong>on</strong>diti<strong>on</strong> and a predicti<strong>on</strong> is made for possible<br />
negative c<strong>on</strong>sequences of radioactive c<strong>on</strong>taminati<strong>on</strong> to the populati<strong>on</strong> of the former STS.<br />
4) 40218 – RFID Technology for Envir<strong>on</strong>mental Remediati<strong>on</strong> and Radioactive Waste Management<br />
Hanchung Tsai, Yung Liu, ANL (USA); James Shuler, US DOE (USA)<br />
We have developed an advanced Radio Frequency IDentificati<strong>on</strong> (RFID) system capable of tracking and m<strong>on</strong>itoring a wide<br />
range of materials and comp<strong>on</strong>ents for the nuclear industry – from fissi<strong>on</strong>able stocks to radioactive wastes. <str<strong>on</strong>g>The</str<strong>on</strong>g> RFID technology has a<br />
number of advantages, such as enhanced safety and security, reduced pers<strong>on</strong>nel exposure to radiati<strong>on</strong>s, and improved inventory c<strong>on</strong>trol.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> sensors in the RFID tags m<strong>on</strong>itor the state of health (e.g., temperature, shock, seal, dose, and dose rate) of the item and send out an<br />
alarm instantly when the sensor threshold is violated. N<strong>on</strong>volatile memories in the tag store data from sensors and event records, as<br />
well as manifest informati<strong>on</strong> if so desired. In irradiati<strong>on</strong> tests, the tag electr<strong>on</strong>ics was c<strong>on</strong>firmed to possess significant radiati<strong>on</strong><br />
resistance and, therefore, would yield a satisfactory service life. L<strong>on</strong>g-life batteries and smart management circuitries permit the RFID<br />
tags to operate for up to 10 years without a battery replacement. <str<strong>on</strong>g>The</str<strong>on</strong>g> form factor of the tags can be modified to suit different c<strong>on</strong>tainer<br />
types. <str<strong>on</strong>g>The</str<strong>on</strong>g> read range can be up to 100 m, and no line-of-sight between the tagged items and the interrogator (reader) is necessary.<br />
With careful implementati<strong>on</strong>, even a large-size processing or storage facility with a complex c<strong>on</strong>figurati<strong>on</strong> can be m<strong>on</strong>itored with a<br />
handful of readers in a network. In transportati<strong>on</strong>, by using Global Positi<strong>on</strong>ing System (GPS) and satellite/cellular communicati<strong>on</strong><br />
protocols, the locati<strong>on</strong>s and the c<strong>on</strong>diti<strong>on</strong>s of the tagged c<strong>on</strong>tainers can be c<strong>on</strong>tinuously tracked. <str<strong>on</strong>g>The</str<strong>on</strong>g> RFID system also integrates<br />
Geographic Informati<strong>on</strong> Systems (GIS) technology, which uses informati<strong>on</strong> in preexisting geodatabases to generate and issue reports<br />
instantly to first resp<strong>on</strong>ders for situati<strong>on</strong> recovery in case of incidents. In stand-al<strong>on</strong>e applicati<strong>on</strong>s, the m<strong>on</strong>itoring and tracking data are<br />
c<strong>on</strong>tained within the local c<strong>on</strong>trol computer; with a secure Internet c<strong>on</strong>necti<strong>on</strong>, multiple users can share the data in real time within the<br />
complex or bey<strong>on</strong>d. As with the deployment of any new technology, overcoming the cultural resistance is part of the developmental<br />
process. With a str<strong>on</strong>g instituti<strong>on</strong>al support and multiple c<strong>on</strong>vincing live dem<strong>on</strong>strati<strong>on</strong>s, the cultural resistance has been largely<br />
overcome. As a result, implementati<strong>on</strong> of the RFID technology is taking place at several of U.S. Department of Energy installati<strong>on</strong>s for<br />
processing, storage, and transportati<strong>on</strong> applicati<strong>on</strong>s.<br />
5) 40181 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Radioactivity of 3H in Metals by a High Temperature Furnace and a Liquid Scintillati<strong>on</strong> Counter<br />
Hee Reyoung Kim, Geun Sik Choi, Sang Yun Park, Chang Woo Lee, Mo<strong>on</strong> Hee Han, KAERI (Korea Rep.)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> radioactivity of 3H of the metal samples from the nuclear sites was analyzed by using a commercialized high<br />
temperature furnace and a Liquid Scintillati<strong>on</strong> Counter (LSC). <str<strong>on</strong>g>The</str<strong>on</strong>g> 3H activity of the sample was measured according to<br />
the durati<strong>on</strong> of the high temperature combusti<strong>on</strong> and the oxidati<strong>on</strong> temperature. Basically, the recovery from the furnace<br />
was 90% for 3H and the LSC had a quenching efficiency of approximately 30 %. HNO3 was used as a trapping soluti<strong>on</strong><br />
for 3H and the soluti<strong>on</strong> was cocktailed with a scintillator. <str<strong>on</strong>g>The</str<strong>on</strong>g> activity extracted from the sample was increased till the<br />
combusti<strong>on</strong> time elapsed 60 minutes and the increasing rate was reduced c<strong>on</strong>tinuously thereafter at 600 degree in<br />
centigrade whereas 80 % of radioactivity was extracted during the first 15 minutes at 900 degree in centigrade. Also, the<br />
pretreatment for the metal sample, which included a high temperature combusti<strong>on</strong> and trapping, had the time required of<br />
at least four hours at 900 degree in centigrade. Finally, it was suggested that this high temperature combusti<strong>on</strong> method<br />
could be applied to analyze the activity of the radioactive metal waste from the nuclear power plants.<br />
53
Abstracts<br />
6) 40275 – Next Generati<strong>on</strong> Waste Glass Melters in the U.S. DOE Waste Processing Program<br />
Steven P. Schneider, Gary Smith, US DOE (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> USA Department of Energy (U.S. DOE) Office of Envir<strong>on</strong>mental Management (EM) is evaluating alternative<br />
opti<strong>on</strong>s for waste glass melting technologies. Specifically, DOEEM is assessing advanced melter technologies and<br />
developing a comprehensive research plan for next generati<strong>on</strong> waste glass melter design and dem<strong>on</strong>strati<strong>on</strong>. Resoluti<strong>on</strong><br />
of the USA nuclear waste legacy requires the design, c<strong>on</strong>structi<strong>on</strong> and operati<strong>on</strong> of large and technically complex<br />
<strong>on</strong>e-of-a-kind processing facilities coupled to equally complex waste treatment and vitrificati<strong>on</strong> facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g> loading of<br />
nuclear waste into glass and the glass producti<strong>on</strong> rates at U.S. vitrificati<strong>on</strong> facilities are limited by the current melter<br />
technology. Significant reducti<strong>on</strong>s in glass volumes for disposal and missi<strong>on</strong> life are <strong>on</strong>ly possible with advancements in<br />
melter technology and glass formulati<strong>on</strong>s. Melters with higher throughput rate may shorten cleanup missi<strong>on</strong>, in additi<strong>on</strong><br />
melters that allow for higher waste loading in glass may significantly reduce lifecycle costs.<br />
To help focus the next generati<strong>on</strong> waste glass melter program, DOE-EM c<strong>on</strong>vened an internati<strong>on</strong>al workshop to<br />
assess nuclear waste melter technologies and have used the melter workshop to help develop a comprehensive research<br />
plan for melter design and dem<strong>on</strong>strati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> workshop included both oral presentati<strong>on</strong>s and discussi<strong>on</strong> sessi<strong>on</strong>s from<br />
waste glass melter experts from around the world to assess the "state of the art" in melter technology and to lay the<br />
groundwork for a program plan that includes evoluti<strong>on</strong>ary changes to existing Joule-heated ceramic-lined liquid fed<br />
melters, as well as transformati<strong>on</strong>al melter technologies such as inducti<strong>on</strong> and hybrid-heated systems. At that workshop,<br />
representatives from many nati<strong>on</strong>s and internati<strong>on</strong>al organizati<strong>on</strong>s (IAEA, China, France, Germany, India, Japan, Korea,<br />
Russia, UK, and the USA), universities (Catholic University of America, Missouri University of Science and<br />
Technology), and private companies (EnergySoluti<strong>on</strong>s, Kuri<strong>on</strong>, URS) met to assess advanced melter technologies which<br />
helped the U.S. develop a comprehensive research plan for advanced waste glass melter design and dem<strong>on</strong>strati<strong>on</strong> with<br />
the goal of improved performance and reduced cost. <str<strong>on</strong>g>The</str<strong>on</strong>g> U.S. DOE Next Generati<strong>on</strong> Waste Glass Melter Program is<br />
discussed in this paper.<br />
SESSION L2: Solidificati<strong>on</strong> and Package (1)<br />
1) 40021 – Commercializati<strong>on</strong> Project of Ulchin Vitrificati<strong>on</strong>�<br />
Hyun-jun Jo, Che<strong>on</strong>-Woo Kim, KHNP (Korea Rep.);<br />
Tae-W<strong>on</strong> Hwang, Nuclear Engineering & Technology Institure (Korea Rep.)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Ulchin Vitrificati<strong>on</strong> Facility (UVF), to be used for the vitirificati<strong>on</strong> of low-and intermediate-level radioactive<br />
waste (LILW) generated by nuclear power plants (NPPs), is the world’s first commercial facility using Cold Crucible<br />
Inducti<strong>on</strong> Melter (CCIM) technology. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>structi<strong>on</strong> of the facility was begun in 2005 and was completed in 2007.<br />
From December 2007 to September 2009, all key performance tests, such as the system functi<strong>on</strong>al test, the cold test, the<br />
hot test, and the real waste test, were successfully carried out. <str<strong>on</strong>g>The</str<strong>on</strong>g> UVF commenced commercial operati<strong>on</strong> in October<br />
2009 for the vitrificati<strong>on</strong> of radioactive waste.<br />
2) 40023 – Plasma Gasificati<strong>on</strong>/Vitrificati<strong>on</strong> of Wet ILW<br />
Gary Hanus, John Williams, Matt Zirbes, Phoenix Soluti<strong>on</strong>s Co. (USA)<br />
Magnox South Ltd has authorized a variety of decommissi<strong>on</strong>ing programmes to evaluate various technologies for<br />
timely and cost-effective remediati<strong>on</strong> of a spectrum of waste streams resulting from the operati<strong>on</strong> of their reactors. Of<br />
particular current interest is wet, intermediate level waste (ILW) in the form of solids, sludges and liquids. Hinkley Point<br />
A has over 137,000 litres of ILW organic cati<strong>on</strong> resin c<strong>on</strong>taining significant quantities of radio-cesium (Cs). In 2009<br />
Phoenix Soluti<strong>on</strong>s Co was awarded a c<strong>on</strong>tract by Magnox South Ltd to dem<strong>on</strong>strate the effectiveness of thermal plasma<br />
treatment of this wet ILW resin waste stream.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> objective of the wet ILW plasma treatment project was to feed organic resin sludge (c<strong>on</strong>taining a cesium<br />
surrogate) and a borosilicate glass frit simultaneously into a thermal plasma reactor to dem<strong>on</strong>strate the gasificati<strong>on</strong> of the<br />
organic c<strong>on</strong>tent of the resin while capturing the cesium within a molten glass bath. A total of approximately 200 litres of<br />
glass product were produced. Approximately 5 metric t<strong>on</strong>nes of organic resin simulant were provided to Phoenix<br />
Soluti<strong>on</strong>s Co c<strong>on</strong>sisting of a mixture of 68% water / NaOH soluti<strong>on</strong>, 30% organic cati<strong>on</strong> resin material with bound Cs<br />
and 2% other, including a small proporti<strong>on</strong> of cesium in soluti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> off-gas species from the plasma reactor exhaust<br />
were sampled by an independent, qualified sampling organizati<strong>on</strong> focusing <strong>on</strong> VOCs, HCl, NOx, SOx, CO, CO2, dioxins<br />
and furans as well as particulate levels. Glass samples were obtained and analyzed for crystalline inclusi<strong>on</strong>s, elemental<br />
identificati<strong>on</strong>, and viscosity characteristics at temperatures near the process melt c<strong>on</strong>diti<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> process temperature was<br />
maintained near 1000 ºC while the molten glass bath was held between 1100 and 1200 ºC. <str<strong>on</strong>g>The</str<strong>on</strong>g> processing produced 200<br />
litres of glass, 150 litres of which were successfully tapped from the plasma reactor into a standard Sellafield vitrified<br />
HLW disposal canister.<br />
This paper will describe the basic waste processing approach, the process hardware utilized, the process c<strong>on</strong>trol<br />
features and the test results. Several trial tests were c<strong>on</strong>ducted, the l<strong>on</strong>gest of which processed over 2 metric t<strong>on</strong>nes of<br />
54
Abstracts<br />
dewatered resin waste together with 400 kg of glass. Further testing with improved process c<strong>on</strong>trols dem<strong>on</strong>strated an<br />
increase in cesium retenti<strong>on</strong> in the glass product.<br />
3) 40026 – Solidificati<strong>on</strong> Of Simulated Liquid Waste Of Primary Loop Resin Eluti<strong>on</strong> Process Of PWR<br />
Masamichi Obata, Michitaka Saso, Masaaki Kaneko, Nobuhito Ogaki, Taichi Horimoto,<br />
Toshiba corporati<strong>on</strong> (Japan);Toshikazu Waki, <str<strong>on</strong>g>The</str<strong>on</strong>g> Kansai Electirc Power Co., Inc. (Japan)<br />
Primary loop resin waste is eluted by sulfuric acid in <str<strong>on</strong>g>The</str<strong>on</strong>g> Kansai Electic Company Mihama,Takahama and Oi<br />
nuclear power stati<strong>on</strong>. Waste soluti<strong>on</strong> from this eluti<strong>on</strong> process is planned to be solidified by cement. This study bring<br />
out a range of chemical compositi<strong>on</strong> and crud c<strong>on</strong>centrati<strong>on</strong> of waste soluti<strong>on</strong> from this eluti<strong>on</strong> process, and examine the<br />
properties of alumina cement solidificati<strong>on</strong> process and solidified material. Test for sulfate i<strong>on</strong>, borate, lithium,<br />
amm<strong>on</strong>ium i<strong>on</strong> was carried out. Volume reducti<strong>on</strong> ratio of over 0.5 was archieved for 5 to 25wt% of sulfate i<strong>on</strong> and<br />
Abstracts<br />
SESSION L3: Nuclide Assay<br />
1) 40279 – Design of a facility for the automated receipt inspecti<strong>on</strong> and characterizati<strong>on</strong> of LILW using<br />
integrated n<strong>on</strong>-destructive examinati<strong>on</strong> and assay techniques<br />
Stephen Halliwell, VJ Technologies Inc.� (USA)<br />
KHNP is c<strong>on</strong>structing two repositories, located in B<strong>on</strong>ggil-ri, Yangbukmyun, Gye<strong>on</strong>gju-si, Gye<strong>on</strong>gbuk, Korea, for<br />
Low & Intermediate Level Radwaste. (LILW). <str<strong>on</strong>g>The</str<strong>on</strong>g> waste received is required to be inspected and characterized prior to<br />
being placed into storage at the repository. This paper describes the design of an integrated system of n<strong>on</strong> destructive<br />
examinati<strong>on</strong> (xray), and n<strong>on</strong> destructive assay (radiometric) instrument systems, waste package integrity checking<br />
systems, waste handling mechanisms and data management and archival provisi<strong>on</strong>s, which comprise the Waste Receipt<br />
and Inspecti<strong>on</strong> Facility (WRIF). <str<strong>on</strong>g>The</str<strong>on</strong>g> WRIF is designed to uncap transport c<strong>on</strong>tainers, unload waste drums from<br />
c<strong>on</strong>tainers, safely examine the drums, to ensure they meet the waste acceptance criteria established by the LILW facility.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> drums are then loaded into waste disposal c<strong>on</strong>tainers for transfer to the repository. <str<strong>on</strong>g>The</str<strong>on</strong>g> WRIF also receives larger<br />
waste c<strong>on</strong>tainers, which are characterized in a separate secti<strong>on</strong> of the WRIF, before being transferred to the repository.<br />
Remote c<strong>on</strong>trol and handling of the waste is a design requirement, as is the management, processing archival and<br />
retrieval system for all data generated during waste characterizati<strong>on</strong>.<br />
Importance of this work<br />
Remotely c<strong>on</strong>trolled characterizati<strong>on</strong> of LILW in drums and large boxes, by the integrated system of<br />
n<strong>on</strong>-destructive and n<strong>on</strong>-intrusive techniques in the WRIF, will minimize the risk of operator dose uptake, increase<br />
operator safety, reduce the generati<strong>on</strong> of additi<strong>on</strong>al waste, and save time and cost within the waste management process.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> data management, processing, archival and retrieval system will insure the data quality and integrity is maintained<br />
over the required period of time, and that particular data can be easily and reliably accessed at any time.<br />
2) 40167 – Feasibility Study <strong>on</strong> the Nuclide Analysis of the Radwaste Drum Using the Spectrum to Dose<br />
C<strong>on</strong>versi<strong>on</strong> Factor<br />
Young-Y<strong>on</strong>g Ji, Dae-Seok H<strong>on</strong>g, Tae-kuk Kim, Woo-Seog Ryu, KAERI (Korea Rep.)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>re are several methods for n<strong>on</strong>-destructive assay of a radwaste drum that are based <strong>on</strong> the gamma ray scanning<br />
and the in-situ objet counting system. Although these methods can be processed using high resoluti<strong>on</strong>, shielded detector<br />
and specific correcti<strong>on</strong> techniques to quantitatively analyze the nuclides in a drum, time and cost c<strong>on</strong>straints compared<br />
with their accuracy dictate the use of simpler method to apply. Dose to curie (DTC) c<strong>on</strong>versi<strong>on</strong> method can simply and<br />
easily provide a reas<strong>on</strong>able estimate of the nuclide inventory in a radwaste drum. <str<strong>on</strong>g>The</str<strong>on</strong>g> measured dose rate as well as the<br />
relative abundance of gamma nuclides in a drum is a very important factor to be appreciated at the DTC c<strong>on</strong>versi<strong>on</strong><br />
method because of the direct linearity between the measured dose rate and the gamma emitters in a drum. <str<strong>on</strong>g>The</str<strong>on</strong>g> dose rate is<br />
directly measured with the field detector. However, the relative abundance of gamma nuclides in a drum to be assayed is<br />
determined form an indirect measurement using the material balance by the waste stream. <str<strong>on</strong>g>The</str<strong>on</strong>g> uncertainty of the nuclide<br />
inventory of the assayed drum from the DTC c<strong>on</strong>versi<strong>on</strong> method could be increased because of the different detecti<strong>on</strong><br />
mechanism between the dose rate and the relative abundance of gamma emitters in a drum. Unfortunately, that expands<br />
the limitati<strong>on</strong> of using the DTC method. It is, therefore, necessary to find out a suitable measurement method of which<br />
two variables could be obtained from the drum to be assayed at <strong>on</strong>ce. This method could be realized by using the dose<br />
c<strong>on</strong>versi<strong>on</strong> factor, which has been widely using in the field of the envir<strong>on</strong>mental radiati<strong>on</strong> measurement. <str<strong>on</strong>g>The</str<strong>on</strong>g> dose rate<br />
from a drum could be directly calculated from the measured gamma ray spectra by using the dose c<strong>on</strong>versi<strong>on</strong> factor, and<br />
also, the relative abundance of gamma nuclides could be easily obtained from the net count peaks in the spectra. In this<br />
study, the dose c<strong>on</strong>versi<strong>on</strong> factor for 3”?x3” NaI(Tl) scintillati<strong>on</strong> detector around lead shield with the thickness of about<br />
3 cm was calculated by a MCNP code. <str<strong>on</strong>g>The</str<strong>on</strong>g> experimental verificati<strong>on</strong> for using this dose c<strong>on</strong>versi<strong>on</strong> factor was performed<br />
by using the simulated drum that has several holes for locating a standard source.<br />
3) 40255 – Portable N<strong>on</strong>-Destructive Assay Methods for Screening and Segregati<strong>on</strong> of Radioactive Waste<br />
Alan Simps<strong>on</strong>, Martin Clapham, Stephanie J<strong>on</strong>es, Randy Lucero, Pajarito Scientific Corporati<strong>on</strong> (UK)<br />
Significant cost-savings and operati<strong>on</strong>al efficiency may be realised by performing rapid n<strong>on</strong>destructive<br />
classificati<strong>on</strong> of radioactive waste at or near its point of retrieval or generati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g>re is often a need to quickly<br />
categorize and segregate bulk c<strong>on</strong>tainers (drums, crates etc.) into waste streams defined at various boundary levels (based<br />
<strong>on</strong> its radioactive hazard) in order to meet disposal regulati<strong>on</strong>s and c<strong>on</strong>signor waste acceptance criteria.<br />
Recent improvements in gamma spectroscopy technologies have provided the capability to perform rapid in-situ<br />
analysis using portable and hand-held devices such as battery-operated medium and high resoluti<strong>on</strong> detectors including<br />
lanthanum halide and high purity germanium (HPGe). Instruments and technologies that were previously the domain of<br />
complex lab systems are now widely available as touch-screen “off-the-shelf” units. Despite such advances, the task of<br />
waste stream screening and segregati<strong>on</strong> remains a complex exercise requiring a detailed understanding of programmatic<br />
requirements and, in particular, the capability to ensure data quality when operating in the field. This is particularly so<br />
when surveying historical waste drums and crates c<strong>on</strong>taining heterogeneous debris of unknown compositi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> most<br />
56
Abstracts<br />
widely used portable assay method is based up<strong>on</strong> far-field High Resoluti<strong>on</strong> Gamma Spectroscopy (HRGS) assay using<br />
HPGe detectors together with a well engineered deployment cart (such as the PSC TechniCART technology).<br />
Hand-held Sodium Iodide (NaI) detectors are often also deployed and may also be used to supplement the HPGe<br />
measurements in locating hot spots. Portable neutr<strong>on</strong> slab m<strong>on</strong>itors may also be utilised in cases where gamma<br />
measurements al<strong>on</strong>e are not suitable.<br />
Several case histories are discussed at various sites where this equipment has been used for in-situ characterizati<strong>on</strong><br />
of debris waste, sludge, soil, high activity waste, depleted and enriched uranium, heat source and weap<strong>on</strong>s grade<br />
plut<strong>on</strong>ium, fissi<strong>on</strong> products, activati<strong>on</strong> products, americium, curium and other more exotic nuclides. <str<strong>on</strong>g>The</str<strong>on</strong>g> process of<br />
acquiring and analyzing data together with integrati<strong>on</strong> of historical knowledge to resolve and delineate waste streams (for<br />
example between low-level waste and transuranic waste) is described.<br />
4) 40093 – Alpha radioactivity m<strong>on</strong>itor using i<strong>on</strong>ized air transportati<strong>on</strong> for large size uranium waste (1) - Large<br />
measurement chamber and evaluati<strong>on</strong> of detecti<strong>on</strong> performance –<br />
Susumu Naito, Shuji Yamamoto, Miikio Izumi, Yosuke Hirata,<br />
Yukio Yoshimura, Tatsuyuki Maekawa,Toshiba Corporati<strong>on</strong> (Japan)<br />
Massive amounts of waste c<strong>on</strong>taminated with alpha-radioactive uranium have accumulated in back-end facilities of<br />
the nuclear fuel cycle. In order to dispose of it adequately, it is necessary to classify such waste according to its so-called<br />
clearance level. However, when measuring alpha radioactivity using a c<strong>on</strong>venti<strong>on</strong>al survey meter, <strong>on</strong>e must hold it as<br />
close as possible to the surface, due to the relatively short flight range of alpha particles in air. As a result, measuring a<br />
large amount of diverse waste takes a l<strong>on</strong>g time and involves high labor costs. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, a new efficient alpha<br />
measurement technique is str<strong>on</strong>gly desired. To satisfy this demand, we have been developing an alpha radioactivity<br />
m<strong>on</strong>itor based <strong>on</strong> the principle of alpha radioactivity measurement using i<strong>on</strong>ized air transportati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> measurement<br />
principle is as follows. Air is i<strong>on</strong>ized by alpha particles emitted from the waste. <str<strong>on</strong>g>The</str<strong>on</strong>g> produced i<strong>on</strong>s are transported to an<br />
i<strong>on</strong> sensor with the air flow produced by a blower, where the number of i<strong>on</strong>s is measured as an electric current (i<strong>on</strong><br />
current). <str<strong>on</strong>g>The</str<strong>on</strong>g> alpha radioactivity is then evaluated from the i<strong>on</strong> current value. This indirect measurement method is very<br />
efficient, because the i<strong>on</strong>s produced near the entire surface of the waste can be detected both all at <strong>on</strong>ce and at a distant<br />
positi<strong>on</strong> from the waste. In previous work, we developed a prototype m<strong>on</strong>itor with an about 1000 mm cubic measurement<br />
chamber to measure the cut waste. However, in a survey of target waste, we found that it is desired to measure not <strong>on</strong>ly<br />
the cut waste but also the lengthy waste such as uncut cylinders. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, we developed an alpha radioactivity m<strong>on</strong>itor<br />
with a l<strong>on</strong>g and large measurement chamber (effective sizes: 500 mm x 900 mm x 3200 mm) for the l<strong>on</strong>g and large<br />
cylindrically-shaped waste (maximum size: 300 mm in diameter and 3000 mm in length, weight: 10 to 200 kg). We<br />
aimed
Abstracts<br />
6) 40111 – Preparati<strong>on</strong> of Reference Materials <strong>on</strong> Radiochemical Analysis for Low-Level Radioactive Waste<br />
Generated from Japan Atomic Energy Agency<br />
Ken-ichiro Ishimori, Mikio Nakashima, Kuniaki Takahashi, Yutaka Kameo, JAEA (Japan)<br />
We have advanced the development of simple and rapid determinati<strong>on</strong> method for important radi<strong>on</strong>uclides <strong>on</strong> safety<br />
assessment for disposal of low-level radioactive wastes generated from Japan Atomic Energy Agency (JAEA). In the<br />
radiochemical analyses of the radioactive wastes, it is necessary to manage accuracy and precisi<strong>on</strong> of determined values<br />
of radioactivity c<strong>on</strong>centrati<strong>on</strong> using reference materials. However, since appropriate reference materials of radioactive<br />
waste are hardly available at the present state, the developments of laboratory-scale preparati<strong>on</strong> methods are required to<br />
supply reference materials. In this work, we investigated preparati<strong>on</strong> methods for the reference materials c<strong>on</strong>taining<br />
important nuclides and c<strong>on</strong>firmed the validity of the prepared materials. Additi<strong>on</strong>ally a reference material for cemented<br />
liquid waste was also prepared. --Solidified product c<strong>on</strong>taining alpha-ray and gamma-ray emitting nuclides--In waste<br />
management in JAEA, n<strong>on</strong>-metallic low-level radioactive solid wastes will be treated by plasma melting at the Advanced<br />
Volume Reducti<strong>on</strong> Facilities (AVRF). In order to clarify optimum melting c<strong>on</strong>diti<strong>on</strong>s of solidified products using a<br />
laboratory-scale electric furnace instead of plasma heating device, we c<strong>on</strong>ducted melting tests of a miscellaneous<br />
simulated solid waste in the presence of stable isotope tracers. Over 90% of Cs remained in the solidified product by<br />
keeping the basicity (CaO[wt%] / SiO2[wt%]) to be 0.05. Under the optimum melting c<strong>on</strong>diti<strong>on</strong>s, we prepared reference<br />
materials c<strong>on</strong>taining alpha-ray (237Np, 241Am, and 244Cm) and gamma-ray (60Co, 137Cs, and 152Eu) emitting<br />
nuclides. <str<strong>on</strong>g>The</str<strong>on</strong>g> characteristics observed in SEM-EDX measurement and chemical durability against acids suggested that<br />
glass structure of the reference materials was almost same as that of solidified products produced by plasma melting.<br />
--Solidified product c<strong>on</strong>taining 14C or 36Cl-- Since 14C and 36Cl easily vaporize at a high temperature, it is difficult to<br />
remain the nuclides in solidified product <strong>on</strong> melting treatment with an electric furnace. First, melting c<strong>on</strong>diti<strong>on</strong>s for<br />
solidified glasses c<strong>on</strong>taining N or Cl were optimized. We attempted a preparati<strong>on</strong> method which produces 14C or 36Cl in<br />
the solidified glass using nuclear reacti<strong>on</strong> 14N(n, p)14C or 35Cl(n, gamma)36Cl by thermal neutr<strong>on</strong> irradiati<strong>on</strong>.<br />
Reference materials c<strong>on</strong>taining 14C or 36Cl were successfully prepared by the proposed method. <str<strong>on</strong>g>The</str<strong>on</strong>g> radioactivity<br />
c<strong>on</strong>centrati<strong>on</strong>s of the reference materials were evaluated from the developed simple and rapid determinati<strong>on</strong> method.<br />
From the results, it was c<strong>on</strong>firmed that reference materials, which was useful for routine radiochemical analysis, could be<br />
successfully prepared <strong>on</strong> the present preparati<strong>on</strong> methods.<br />
SESSION H4: Nati<strong>on</strong>al and <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Programs (2)<br />
1) 40213 – U.S. NRC Integrated Spent Fuel Management Plan<br />
Catherine Haney, Shawn Smith, US NRC (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> U.S. Nuclear Regulatory Commissi<strong>on</strong> (NRC) is developing an integrated plan for regulating the interrelated<br />
activities that are involved in the management of spent fuel and high-level waste. Treating the system as a whole is<br />
essential for several reas<strong>on</strong>s: (1) decisi<strong>on</strong>s made about <strong>on</strong>e comp<strong>on</strong>ent or activity of the waste management system could<br />
significantly affect other comp<strong>on</strong>ents (e.g., a decisi<strong>on</strong> made in isolati<strong>on</strong> could inadvertently impact alternatives to the<br />
system as a whole); (2) treating waste management as a system is a more efficient and effective way to determine<br />
priorities, logically complete activities or to appropriately deal with unexpected situati<strong>on</strong>s that may arise with<br />
first-of-a-kind programs like reprocessing or alternative waste disposal opti<strong>on</strong>s; and (3) viewing the system as a whole<br />
avoids gaps and unnecessary duplicati<strong>on</strong> in regulati<strong>on</strong>s leading to more effective and efficient development and<br />
applicati<strong>on</strong> of regulatory oversight.<br />
Near-term flexibility is a key c<strong>on</strong>siderati<strong>on</strong> because the nati<strong>on</strong>al policy in the USA appears to be changing and will<br />
likely remain in flux for some time. For example, the Secretary of Energy has c<strong>on</strong>vened a commissi<strong>on</strong> to c<strong>on</strong>duct a<br />
comprehensive review of the policies for managing the back end of the nuclear fuel cycle. NRC activities will be<br />
informed by this and other relevant developments as it develops its plans. However, integrati<strong>on</strong> is essential regardless of<br />
the directi<strong>on</strong> of nati<strong>on</strong>al policy, as the NRC needs to remain flexible and agile under a range of policy outcomes. This<br />
presentati<strong>on</strong> will describe key aspects of the plan and how the plan will be implemented.<br />
2) 40116 – Regulatory Research for Geological Disposal of High-level Radioactive Waste in Japan<br />
Shinichi Nakayama, JAEA (Japan); Yoshio Watanabe, AIST (Japan); Masami Kato, JNES (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Nuclear and Industrial Safety Agency of the Ministry of Ec<strong>on</strong>omy, Trade and Industry (NISA) has renewed its<br />
regulatory role and supporting research needs, taking into c<strong>on</strong>siderati<strong>on</strong> recent circum-stances of radioactive waste<br />
management in Japan. In October 2009, a technical support organizati<strong>on</strong> of the Japan Nuclear Energy Safety<br />
Organizati<strong>on</strong> (JNES) released its independent five-year research plan, “Regulatory Support Research Plan <strong>on</strong> Radioactive<br />
Waste Management 2010-2014”, in cooperati<strong>on</strong> with the research institutes of Japan Atomic Energy Agency (JAEA) and<br />
the Nati<strong>on</strong>al Institute of Advanced In-dustrial Science and Technology (AIST). <str<strong>on</strong>g>The</str<strong>on</strong>g> plan covers low- through high-level<br />
radioactive waste management. <str<strong>on</strong>g>The</str<strong>on</strong>g> geological disposal research plan and the future research activities are outlined in<br />
this paper. Japan’s nuclear regulati<strong>on</strong> law, “Law for Regulati<strong>on</strong> of Nuclear Source Materials, Nuclear Fuel Ma-terials and<br />
58
Abstracts<br />
Nuclear Reactors”, was amended in 2007 to address the safety of geologic disposal of high-level radioactive waste. NISA<br />
announced its involvement or supervisi<strong>on</strong> not <strong>on</strong>ly for the licensing applicati<strong>on</strong> but during the site selecti<strong>on</strong> process. Two<br />
major research areas required by NISA have been identified: studies to review the validity of preliminary survey results<br />
during the site selecti<strong>on</strong>, and studies to review the safety assessment for a licensing applicati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g>se research areas are<br />
aimed at 1) developing “safety indicators” to judge the adequacy of site investigati<strong>on</strong> results presented by the operator, 2)<br />
compiling basic requirements of safety design and safety assessment needed to make a technical evaluati<strong>on</strong> of the license<br />
applicati<strong>on</strong>, as well as developing safety indicators for objective evaluati<strong>on</strong>, and 3) developing an inde-pendent safety<br />
assessment methodology. In additi<strong>on</strong>, NISA plans to periodically issue the report, “<str<strong>on</strong>g>The</str<strong>on</strong>g> Regulatory Research Report <strong>on</strong><br />
Geological Disposal” c<strong>on</strong>sistent with the operator’s technical report sched-ule. This report would be intended to c<strong>on</strong>firm<br />
the regulatory status of the program as well as strengthen-ing the competence of NISA as a regulatory body. JNES<br />
launched safety studies <strong>on</strong> geological disposal in its establishment year in 2003. JAEA and AIST joined as regulatory<br />
support research institutes in 2005. In October 2007, the three parties signed an agreement of cooperative study <strong>on</strong><br />
geological disposal, which enhanced joint studies, as well as exchanges of staff, data, and results. One of the <strong>on</strong>going<br />
joint studies has been aimed at investigating regi<strong>on</strong>al-scale hydrogeological modeling using JAEA’s Hor<strong>on</strong>obe<br />
Underground Research Center. <str<strong>on</strong>g>The</str<strong>on</strong>g> three parties have begun to discuss expanding the joint studies and the agreement<br />
areas in resp<strong>on</strong>se to the new five-year re-search plan.<br />
3) 40280 – Recent Developments and Trends <strong>on</strong> Requirements Management Systems<br />
Satoru Suzuki, Hiroyoshi Ueda, Kiyoshi Fujisaki, Katsuhiko Ishiguro, Hiroyuki Tsuchi, NUMO (Japan);<br />
Stratis Vomvoris,Irina Gaus, Nagra (Switzerland)<br />
Although the management of requirements for the development of geologic repository systems has been practiced in<br />
all radioactive waste disposal programs from the beginning, the systematic management through IT-based requirement<br />
management systems (RMS) has a younger history. Traditi<strong>on</strong>ally requirements have been gathered in various documents<br />
and quite often the rati<strong>on</strong>ale for design choices is difficult to trace. Thanks to the development of RMS in other industries<br />
(software development, aerospace), many radioactive waste disposal programs have recently been able to set-up and<br />
tailor RMS to their needs quickly. In a recent internati<strong>on</strong>al meeting, five radioactive waste disposal organizati<strong>on</strong>s<br />
(NUMO/Japan; NAGRA/Switzerland; ONDRAF/NIRAS/Belgium; POSIVA/Finland and SKB/Sweden) have discussed<br />
the status and developments of RMS in their respective programs. <str<strong>on</strong>g>The</str<strong>on</strong>g> majority have already implemented an IT-based<br />
system, or, are testing and developing such systems. <str<strong>on</strong>g>The</str<strong>on</strong>g> level of detail of requirements depends <strong>on</strong> the stage of the<br />
program. Those approaching the license applicati<strong>on</strong> have integrated all comp<strong>on</strong>ents of the repository c<strong>on</strong>cept, including<br />
the processes for the operati<strong>on</strong>al phase. It was recognized that the earlier you implement a systematic tracking of<br />
requirements and the decisi<strong>on</strong>s taken to satisfy these requirements, the easier it would be to implement an RMS over the<br />
whole durati<strong>on</strong> of the geologic disposal program – in the order of 100 years. <str<strong>on</strong>g>The</str<strong>on</strong>g> documented transiti<strong>on</strong> from the general<br />
requirements (highest level) to the lower level <strong>on</strong>es – especially those related to the repository system c<strong>on</strong>cept or its<br />
comp<strong>on</strong>ents – can be then used to enable the assessment of potential changes at future stages of the system. Even if the<br />
host rock or, the repository c<strong>on</strong>cept has not been selected, a ‘dry’ run with assumed c<strong>on</strong>diti<strong>on</strong>s can be very elucidating of<br />
the most useful set-up of the RMS. Requirements management is closely associated with the quality management system.<br />
Combining requirement and decisi<strong>on</strong>-tracking has been expressed as an explicitly goal for some programs. Cauti<strong>on</strong> was<br />
expressed regarding the expectati<strong>on</strong>s for the RMS being developed. <str<strong>on</strong>g>The</str<strong>on</strong>g>re is a risk that such systems are perceived as<br />
expert systems that can derive decisi<strong>on</strong>s, which then will be unquesti<strong>on</strong>ably accepted. It is nevertheless recognized that<br />
they can be of great help in communicating with the various stakeholders and with relative ease dem<strong>on</strong>strating how their<br />
requirements have been c<strong>on</strong>sidered and satisfied with the proposed repository systems. Further efforts need to be<br />
undertaken to integrate the requirement management systems, and the processes that they represent, in the day-to-day<br />
operati<strong>on</strong>s of the organizati<strong>on</strong>s. Different organizati<strong>on</strong>al schemes are being c<strong>on</strong>sidered, for example, the compositi<strong>on</strong> of<br />
the team that defines the requirements at the various levels and the functi<strong>on</strong> of its members within the technical and<br />
scientific program of the waste disposal organizati<strong>on</strong>s. First positive experiences of the latter were reported.<br />
4) 40228 – Development of Requirements Management System of NUMO and practical experience with<br />
development of the database c<strong>on</strong>tents<br />
Satoru Suzuki, Hiroyoshi Ueda, Katsuhiko Ishiguro, Hiroyuki Tsuchi, Kiyoshi Fujisaki, NUMO (Japan);<br />
Kiyoshi Oyamada, JGC Corporati<strong>on</strong> (Japan); Shoko Yashio, Obayashi Corporati<strong>on</strong> (Japan)<br />
Decisi<strong>on</strong>-making and work activities in the geological disposal program need to be implemented in such a way as to<br />
fulfill various requirements such as safety, practicality, quality and socio-ec<strong>on</strong>omic aspects. Since a stepwise approach is<br />
applied for implementing the program, the number, weighting and specific nature of the requirements will change<br />
depending <strong>on</strong> the premises and c<strong>on</strong>straints in each stage of implementati<strong>on</strong>. Requirements management with a l<strong>on</strong>g-term<br />
perspective is therefore required for c<strong>on</strong>sistent implementati<strong>on</strong> of the program. NUMO has developed a requirements<br />
management (RM) methodology that is suitable for the l<strong>on</strong>g-term, stepwise disposal program in Japan, as well as a<br />
supporting requirements management system (RMS) tool. <str<strong>on</strong>g>The</str<strong>on</strong>g> basic c<strong>on</strong>cept of the RMS was already presented at the<br />
last ICEM 2009. In this presentati<strong>on</strong>, we will focus <strong>on</strong> practical experience with development of the database c<strong>on</strong>tent for<br />
the RMS. <str<strong>on</strong>g>The</str<strong>on</strong>g> RM methodology was first applied in the HLW repository design work. Requirements for repository<br />
design were c<strong>on</strong>sidered primarily from the viewpoint of post-closure safety and engineering feasibility. <str<strong>on</strong>g>The</str<strong>on</strong>g> repository<br />
design requirements are structured hierarchically to those assigned to the ‘post-closure safety c<strong>on</strong>cept’, the ‘required<br />
59
Abstracts<br />
system functi<strong>on</strong>s’ and the ‘design requirements’. <str<strong>on</strong>g>The</str<strong>on</strong>g> post-closure safety c<strong>on</strong>cept, which is based <strong>on</strong> isolati<strong>on</strong> by a<br />
multibarrier system, is further subdivided into fundamental safety functi<strong>on</strong>s and operati<strong>on</strong>al functi<strong>on</strong>s under the heading<br />
‘required system functi<strong>on</strong>s’. <str<strong>on</strong>g>The</str<strong>on</strong>g> fundamental safety functi<strong>on</strong>s are ‘post-closure c<strong>on</strong>tainment’, ‘retardati<strong>on</strong>/reducti<strong>on</strong> of<br />
radi<strong>on</strong>uclide migrati<strong>on</strong>’ and ‘length of migrati<strong>on</strong> pathway’ and they need to be satisfied in order to fulfill the safety<br />
c<strong>on</strong>cept. <str<strong>on</strong>g>The</str<strong>on</strong>g> aim of the operati<strong>on</strong>al functi<strong>on</strong>s is to realize these safety functi<strong>on</strong>s by providing a feasible and reliable<br />
operating system (e.g. welding facility, transport and emplacement). Finally, the lowest level – the design requirements -<br />
are defined for each system comp<strong>on</strong>ent, so that each comp<strong>on</strong>ent can fulfill the upper ranking ‘required system functi<strong>on</strong>s’.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> system comp<strong>on</strong>ents are the engineered barrier system (metal overpack and the bent<strong>on</strong>ite buffer) and the natural<br />
barrier (the host formati<strong>on</strong> and its surroundings). In the NUMO RMS tool, four elements -‘Decisi<strong>on</strong>/Work (D/W)’,<br />
‘Requirements (R)’, ‘C<strong>on</strong>diti<strong>on</strong>s (C)’ and ‘Arguments (A)’ are used for describing the RM informati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> design<br />
requirements discussed above are recorded in the ‘R’ element and attributed to the design work of each comp<strong>on</strong>ent of the<br />
‘D/W’ elements. <str<strong>on</strong>g>The</str<strong>on</strong>g> ‘C’ elements record informati<strong>on</strong> such as the site envir<strong>on</strong>ment, which in turn affects the D/W and R<br />
elements. ‘A’ elements record the synthesis of evidence that fulfills the requirements. <str<strong>on</strong>g>The</str<strong>on</strong>g> database c<strong>on</strong>tent for these four<br />
elements will be defined in advance before initiating the design work in each stage of the disposal program.<br />
5) 40231 – Applicati<strong>on</strong> of Lifecycle Management to Design of the UK Geological Disposal Facility<br />
Henry O'Grady, Malcolm Currie, Pars<strong>on</strong>s Brinckerhoff (UK);<br />
Philip Rendell, Radioactive Waste Management Directorate (UK)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Radioactive Waste Management Directorate (RWMD) of the UK’s (UK) Nuclear Decommissi<strong>on</strong>ing Authority<br />
(NDA) has been charged with the resp<strong>on</strong>sibility for design and delivery of a Geological Disposal Facility (GDF) for High<br />
Level Waste / Intermediate Level Waste in accordance with government policy. Over the next few years, the design of<br />
the GDF will be developed and the organisati<strong>on</strong> built up to provide the necessary design and delivery capability. In the<br />
short term, this capability must also be dem<strong>on</strong>strated to UK government regulators in order to gain approval for nuclear<br />
operati<strong>on</strong>s. As part of this process, RWMD have developed a staged approach to engineering design, which addresses the<br />
overall lifecycle of the GDF in terms of seven phases, from initial c<strong>on</strong>cept development through to operati<strong>on</strong> and, finally,<br />
closure. Each phase finishes with a formally defined milest<strong>on</strong>e (a “gate”) comprising a technical review and a specific set<br />
of engineering deliverables. <str<strong>on</strong>g>The</str<strong>on</strong>g> phases and milest<strong>on</strong>es have been built up from a number standard approaches described<br />
in open literature, which have then been crafted to address the specific needs of the GDF. Roles and resp<strong>on</strong>sibilities are<br />
also c<strong>on</strong>sidered, al<strong>on</strong>g with the interface issues between various functi<strong>on</strong>al groups both within and outside of the<br />
engineering sphere. <str<strong>on</strong>g>The</str<strong>on</strong>g> process also incorporates a number of good practices based <strong>on</strong> the authors’ experiences, such as<br />
requirements management, progressive assurance and the use of architectural frameworks. As the lifecycle of the GDF<br />
will extend over decades, the process uses a modular approach which will permit it to evolve to meet the changing needs<br />
of the project, the organisati<strong>on</strong> and the regulatory process. <str<strong>on</strong>g>The</str<strong>on</strong>g> process is intended to help the engineering effort provide<br />
timely support to, the higher-level needs of the overall project and the community engagement programmes, as well as<br />
with the activities of n<strong>on</strong>-engineering functi<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> process also provides for the management of risk by ensuring that<br />
the requirements, designs, risk registers and detailed procedures are accepted before further funding is released. This<br />
paper describes the background to the UK GDF programme, the organisati<strong>on</strong>al issues associated with the RWMD’s<br />
evolving role, the relati<strong>on</strong>ship between the top-level UK Government Managing Radioactive Waste Safely programme<br />
and the RWMD engineering lifecycle, the formal reviews, the milest<strong>on</strong>es and the overall c<strong>on</strong>tributi<strong>on</strong> this makes to<br />
RWMD organisati<strong>on</strong>al development and UK regulatory approval.<br />
SESSION D2: Dismantling and Dec<strong>on</strong>taminati<strong>on</strong><br />
1) 40036 – AREVA NP: Experience in Dismantling and Packaging of Pressure Vessel and Core Internals<br />
Peter Pillokat, Jan Hendrik Bruhn, AREVA NP GmbH (Germany)<br />
AREVA NP GmbH, German Regi<strong>on</strong>al Sector of French Nuclear Company AREVA is proud to look back <strong>on</strong><br />
versatile experience in successfully dismantling nuclear comp<strong>on</strong>ents. After performing several minor dismantling<br />
projects and studies for nuclear power plants, AREVA NP completed the order to dismantle all remaining reactor<br />
pressure vessel internals at German boiling water reactor Wuergassen NPP in October ´08. During the <strong>on</strong>site activities<br />
about 121 t<strong>on</strong>s of steel where successfully cut and packed under water into 200l- drums, as the dismantling was<br />
performed partly in situ and partly in an underwater working tank. AREVA NP deployed a variety of different cutting<br />
techniques such as band sawing, milling, nibbling, compass sawing and water jet cutting throughout this project. After<br />
successfully finishing this task, AREVA NP is currently dismantling the cylindrical part of the Wuergassen Pressure<br />
Vessel. During this project approxi-mately 320 t<strong>on</strong>s of steel are cut and packaged for final disposal, as dismantling is<br />
mainly performed by <strong>on</strong> air use of water jet cutting with vacuum sucti<strong>on</strong> of abrasive and kerfs material. <str<strong>on</strong>g>The</str<strong>on</strong>g> main clue<br />
during this assignment is the logistic challenge to handle and c<strong>on</strong>vey cut pieces from the pressure vessel to the packing<br />
area. For this an elevator is installed to transport cut segments into the turbine hall, where a special housing is built for<br />
final storage c<strong>on</strong>diti<strong>on</strong>ing. At the beginning of ‘07 another complex dismantling project of great importance was acquired<br />
by AREVA NP. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>tract included dismantling and c<strong>on</strong>diti<strong>on</strong>ing for final storage of all the RPV Internals at German<br />
pressurized water reactor Stade NPP. Very similar cutting techniques turned out to be the proper policy to cope this task.<br />
60
Abstracts<br />
Onsite activities took place in up to 5 separate working areas including areas for post segmentati<strong>on</strong> and packaging to<br />
perform optimized parallel activities. All together about 85 t<strong>on</strong>s of core internals where successfully dismantled at Stade<br />
NPP until September ´09. To accomplish the best possible <strong>on</strong>-site performance and to achieve a minimizati<strong>on</strong> of the<br />
applied collective dose rate, each <strong>on</strong>site activity was previously planned in detail and pers<strong>on</strong>nel exercised each task at<br />
original size mockups under most realistic <strong>on</strong>site c<strong>on</strong>diti<strong>on</strong>s. Planning was especially focused <strong>on</strong> an optimized size<br />
minimizati<strong>on</strong> and packaging c<strong>on</strong>cept to reduce the number of filled waste packages. <str<strong>on</strong>g>The</str<strong>on</strong>g> segmentati<strong>on</strong> of comp<strong>on</strong>ents<br />
strictly followed a sophisticated cutting and packaging c<strong>on</strong>cept developed under c<strong>on</strong>siderati<strong>on</strong> of possible cutting<br />
techniques, the resulting geometry and logistical c<strong>on</strong>diti<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore segments were post processed by hydraulical<br />
press and band saw in order to minimize their volume, were applicable.<br />
2) 40102 – Study <strong>on</strong> evaluati<strong>on</strong> models of management data for decommissi<strong>on</strong>ing of Fugen<br />
Yuji Shibahara, Masanori Izumi, Takashi Nanko, Mitsuo Tachibana, Tsutomu Ishigami, JAEA (Japan)<br />
In the Fugen nuclear power plant (FUGEN), the dismantling of equipments in the turbine building has started in<br />
2008, and the dismantling of equipments around the reactor is scheduled around in 2015. To evaluate the management<br />
data <strong>on</strong> this dismantling of equipments around reactor appropriately, it is very important to study whether the<br />
c<strong>on</strong>venti<strong>on</strong>al evaluati<strong>on</strong> models have the applicability for FUGEN or not. Thus, the management data <strong>on</strong> the dismantling<br />
of equipments in 3rd/4th feedwater heater room c<strong>on</strong>ducted in 2008 was calculated with the c<strong>on</strong>venti<strong>on</strong>al evaluati<strong>on</strong><br />
models. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>venti<strong>on</strong>al evaluati<strong>on</strong> models were made by data obtained from Japan Power Dem<strong>on</strong>strati<strong>on</strong> Reactor<br />
(JPDR) decommissi<strong>on</strong>ing program. It was found that there were large differences between the calculated values and the<br />
actual data. For finding the cause in the difference between them, the dismantling of equipments in 3rd/4th feedwater<br />
heater room was divided into three processes: i) the preparati<strong>on</strong> process, ii) the dismantling process, and iii) the clean-up<br />
process. In the both process of preparati<strong>on</strong> and clean-up, the calculated values were smaller than the actual data. <str<strong>on</strong>g>The</str<strong>on</strong>g>se<br />
were mostly caused by the plant scale difference between JPDR and FUGEN, because the c<strong>on</strong>venti<strong>on</strong>al evaluati<strong>on</strong><br />
models were built by analyzing the actual data <strong>on</strong> the decommissi<strong>on</strong>ing of JPDR which is smaller than FUGEN. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
primary expressi<strong>on</strong> depending <strong>on</strong> the area of working space was built as new evaluati<strong>on</strong> models for the preparati<strong>on</strong> and<br />
clean-up processes. In the dismantling process, <strong>on</strong> the other hand, it was found that there were characteristic differences<br />
in the dismantling of feedwater heater as follows: 1) the calculated values were significantly larger than the actual data,<br />
2) the actual data for the dismantling of 3rd feedwater heater was larger than that of 4th <strong>on</strong>e, though these equipments<br />
were almost same weight. It was found that these were brought by the difference in the descripti<strong>on</strong>s of dismantling of<br />
feedwater heaters, and the new evaluati<strong>on</strong> models reflecting the descripti<strong>on</strong>s of dismantling were built for the appropriate<br />
evaluati<strong>on</strong> of the management data. <str<strong>on</strong>g>The</str<strong>on</strong>g> calculated values with the new evaluati<strong>on</strong> models for each process showed the<br />
good agreement with the actual data. In this report, study <strong>on</strong> evaluati<strong>on</strong> models of management data for dismantling of<br />
equipments in the feedwater heater room will be described.<br />
3) 40083 – CORD Dec<strong>on</strong>taminati<strong>on</strong> Technologies for Decommissi<strong>on</strong>ing - A Comprehensive Approach Based <strong>on</strong><br />
Over 30 Years Experience<br />
Christoph Stiepani, AREVA NP GmbH (Germany)<br />
Dec<strong>on</strong>taminati<strong>on</strong> prior to Decommissi<strong>on</strong>ing and Dismantlement is imperative. Not <strong>on</strong>ly does it provide for<br />
minimizati<strong>on</strong> of pers<strong>on</strong>nel dose exposure but also maximizati<strong>on</strong> of the material volume available for free release. Since<br />
easier dismantling techniques in lower dose areas can be applied, the licensing process is facilitated and the scheduling<br />
and budgeting effort is more reliable. <str<strong>on</strong>g>The</str<strong>on</strong>g> most internati<strong>on</strong>ally accepted approach for Dec<strong>on</strong>taminati<strong>on</strong> prior to<br />
Decommissi<strong>on</strong>ing projects is the Full System Dec<strong>on</strong>taminati<strong>on</strong> (FSD). FSD is defined as the chemical dec<strong>on</strong>taminati<strong>on</strong><br />
of the primary cooling circuit, in c<strong>on</strong>juncti<strong>on</strong> with the main auxiliary systems.<br />
AREVA NP has l<strong>on</strong>g-term experience with Full System Dec<strong>on</strong>taminati<strong>on</strong> for return to service of operating nuclear<br />
power plants as well as for decommissi<strong>on</strong>ing after shutdown. Since 1976, AREVA NP has performed over 500<br />
dec<strong>on</strong>taminati<strong>on</strong> applicati<strong>on</strong>s and, from 1986, AREVA NP has performed Dec<strong>on</strong>taminati<strong>on</strong>s prior to Decommissi<strong>on</strong>ing<br />
projects which comprise virtually all NPP designs and plant c<strong>on</strong>diti<strong>on</strong>s:<br />
- NPP designs: HPWR, PWR, and BWR by AREVA, Westinghouse, ABB and GE<br />
- Dec<strong>on</strong>taminati<strong>on</strong>s performed shortly after final shutdown or several years later, and even after re-opening Safe<br />
Enclosure<br />
- Gamma / Alpha inventory<br />
- Main Coolant chemistry (e.g., with and without Zn injecti<strong>on</strong> during operati<strong>on</strong>)<br />
Fifteen Dec<strong>on</strong>taminati<strong>on</strong> prior to Decommissi<strong>on</strong>ing Projects have been performed successfully to date. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
sixteenth FSD for Decommissi<strong>on</strong>ing at the French NPP Chooz A is now in the detailed engineering phase with <strong>on</strong>site<br />
applicati<strong>on</strong> scheduled for Fall 2010.<br />
This paper will describe the AREVA NP Dec<strong>on</strong>taminati<strong>on</strong> C<strong>on</strong>cept for Decommissi<strong>on</strong>ing (DCD) and present<br />
highlights of previous FSDs performed prior to decommissi<strong>on</strong>ing using the CORD / AMDA technology.<br />
4) 40007 – Chemical Dec<strong>on</strong>taminati<strong>on</strong> for Decommissi<strong>on</strong>ing (DFD) and DFDX<br />
R<strong>on</strong>ald Morris, Westinghouse Electric Company (USA)<br />
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Abstracts<br />
DFD is an acr<strong>on</strong>ym for the “Dec<strong>on</strong>taminati<strong>on</strong> for Decommissi<strong>on</strong>ing” process developed in 1996 by the Electric<br />
Power Research Institute (EPRI). <str<strong>on</strong>g>The</str<strong>on</strong>g> process was designed to remove radioactivity from the surfaces of metallic<br />
comp<strong>on</strong>ents to allow these comp<strong>on</strong>ents to be recycled or free-released for disposal as n<strong>on</strong>-radioactive. DFD is a cyclic<br />
process c<strong>on</strong>sisting of fluroboric acid, potassium permanganate and oxalic acid. <str<strong>on</strong>g>The</str<strong>on</strong>g> process c<strong>on</strong>tinues to uniformly<br />
remove base metal <strong>on</strong>ce oxide dissoluti<strong>on</strong> is complete.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> DFD process has been applied <strong>on</strong> numerous comp<strong>on</strong>ents, sub-systems and systems including the reactor<br />
systems at Big Rock Point and Maine Yankee in the USA, and the Jose Cabrera (Zorita) NPP in Spain. <str<strong>on</strong>g>The</str<strong>on</strong>g> Big Rock<br />
Point site has been returned to Greenfield and at Maine Yankee the land under the license was reduced for an<br />
Independent Spent Fuel Storage Installati<strong>on</strong> (ISFSI). In the upcoming m<strong>on</strong>ths, the Zorita NPP in Spain will initiate<br />
dismantlement and decommissi<strong>on</strong>ing activities to return the site to a n<strong>on</strong>-nuclear facility.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> development of the EPRI DFD process has been an <strong>on</strong>-going evoluti<strong>on</strong> and much has been learned from its use<br />
in the past. It is effective in attaining very high dec<strong>on</strong>taminati<strong>on</strong> factors; however, DFD also produces sec<strong>on</strong>dary waste in<br />
the form of i<strong>on</strong> exchange resins. This sec<strong>on</strong>dary waste generati<strong>on</strong> adds to the decommissi<strong>on</strong>ing quota but can be<br />
improved up<strong>on</strong> at a time when radioactive waste storage at nuclear facilities and waste disposal sites is limited.<br />
To reduce the amount of sec<strong>on</strong>dary waste, EPRI has developed the DFDX process. This new process is an<br />
enhancement to the DFD process and produces a smaller amount of metallic waste rather than resin waste; this reducti<strong>on</strong><br />
in volume being a factor of ten or greater. Electrochemical i<strong>on</strong> exchange cells are the heart of the DFDX system and<br />
c<strong>on</strong>tain electrodes and cati<strong>on</strong> i<strong>on</strong> exchange resin. It has been used very successfully in small system applicati<strong>on</strong>s and the<br />
next evoluti<strong>on</strong> is to design, build and implement a system for the chemical dec<strong>on</strong>taminati<strong>on</strong> for decommissi<strong>on</strong>ing of<br />
larger reactor systems and full system dec<strong>on</strong>taminati<strong>on</strong> (FSD).<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> purpose of this paper will be to provide a reference for those planning future chemical dec<strong>on</strong>taminati<strong>on</strong>s for<br />
plant decommissi<strong>on</strong>ing. It will be based <strong>on</strong> actual experience from the work that has been performed to date and the<br />
planned development of the DFDX process.<br />
5) 40127 – Methods for Calculati<strong>on</strong> and Optimisati<strong>on</strong> of Pers<strong>on</strong>nel Exposure during Planning of<br />
Decommissi<strong>on</strong>ing of Nuclear Installati<strong>on</strong><br />
Marek Vasko, Ivan Rehak, DECOM, a.s. (Slovakia); Vladimir Daniska, DECONTA, a.s. (Slovakia);<br />
Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)<br />
Assessment of pers<strong>on</strong>nel exposure is <strong>on</strong>e of safety issues being evaluated within decommissi<strong>on</strong>ing plans. It is<br />
required to show an impact of planned decommissi<strong>on</strong>ing activities to pers<strong>on</strong>nel and dem<strong>on</strong>strate even at the stage of<br />
decommissi<strong>on</strong>ing planning that the pers<strong>on</strong>nel exposure will be minimized in line with ALARA principle. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper<br />
presents a methodology for evaluati<strong>on</strong> of pers<strong>on</strong>nel exposure developed within standardized decommissi<strong>on</strong>ing costing<br />
code OMEGA. It deals with a methodology for calculati<strong>on</strong> of external and internalpers<strong>on</strong>nel exposure based <strong>on</strong><br />
calculated individual manpower comp<strong>on</strong>ents for each professi<strong>on</strong> within working group and relevant dose rates, the dose<br />
rate from equipment, average dose rate in the rooms and background dose rate, as well as air volume radioactivities of<br />
radi<strong>on</strong>uclides as they are recorded in facility inventory database. It also deals with the methodology for evaluati<strong>on</strong> and<br />
optimizati<strong>on</strong> of the individual effective dose for individual members of working group based <strong>on</strong> their professi<strong>on</strong>.<br />
Developed methodology enables optimizati<strong>on</strong> of deployment for individuals assigned to given professi<strong>on</strong>s within<br />
deployed working group in order to keep the individual effective dose within stipulated limits.<br />
SESSION D3: Planning<br />
1) 40129 – Program Change Management During Nuclear Power Plant Decommissi<strong>on</strong>ing<br />
Mike Naught<strong>on</strong>, Sean Bushart, Karen Kim, EPRI (USA)<br />
Decommissi<strong>on</strong>ing a nuclear power plant is a complex project. <str<strong>on</strong>g>The</str<strong>on</strong>g> project involves the coordinati<strong>on</strong> of several<br />
different departments and the management of changing plant c<strong>on</strong>diti<strong>on</strong>s, programs, and regulati<strong>on</strong>s. As certain project<br />
Milest<strong>on</strong>es are met, the evoluti<strong>on</strong> of such plant programs and regulati<strong>on</strong>s can help optimize project executi<strong>on</strong> and cost.<br />
This paper will provide informati<strong>on</strong> about these Milest<strong>on</strong>es and the plant departments and programs that change<br />
throughout a decommissi<strong>on</strong>ing project. <str<strong>on</strong>g>The</str<strong>on</strong>g> initial challenge in the decommissi<strong>on</strong>ing of a nuclear plant is the<br />
development of a definitive plan for such a complex project. EPRI has published several reports related to<br />
decommissi<strong>on</strong>ing planning. <str<strong>on</strong>g>The</str<strong>on</strong>g>se earlier reports provided general guidance in formulating a Decommissi<strong>on</strong>ing Plan.<br />
This Change Management paper will draw from the experience gained in the last decade in decommissi<strong>on</strong>ing of nuclear<br />
plants. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper discusses decommissi<strong>on</strong>ing in terms of a sequence of major Milest<strong>on</strong>es. <str<strong>on</strong>g>The</str<strong>on</strong>g> plant programs, associated<br />
plans and acti<strong>on</strong>s, and staffing are discussed based up<strong>on</strong> experiences from the following power reactor facilities: Maine<br />
Yankee Atomic Power Plant, Yankee Nuclear Power Stati<strong>on</strong>, and the Haddam Neck Plant. Significant less<strong>on</strong>s learned<br />
from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissi<strong>on</strong>ing projects.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> development of a definitive Decommissi<strong>on</strong>ing Plan can result in c<strong>on</strong>siderable project savings. <str<strong>on</strong>g>The</str<strong>on</strong>g> decommissi<strong>on</strong>ing<br />
plants in the U.S. have planned and executed their projects using different strategies based <strong>on</strong> their unique plant<br />
circumstances. However, experience has shown that similar project milest<strong>on</strong>es and acti<strong>on</strong>s applied through all of these<br />
projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transiti<strong>on</strong>s from an<br />
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Abstracts<br />
operating plant through decommissi<strong>on</strong>ing, the reducti<strong>on</strong> and terminati<strong>on</strong> of defunct programs and regulati<strong>on</strong>s can help<br />
optimize all facets of decommissi<strong>on</strong>ing. This informati<strong>on</strong>, learned through trial in previous plants, can be incorporated<br />
into the decommissi<strong>on</strong>ing plan of future projects so that the benefits of optimizati<strong>on</strong> can be realized from the beginning<br />
of the projects. This process of the collecti<strong>on</strong> of informati<strong>on</strong> and less<strong>on</strong>s learned from plant experiences is an important<br />
functi<strong>on</strong> of the EPRI Decommissi<strong>on</strong>ing Program.<br />
2) 40245 – Status of the Support Researches for the Regulati<strong>on</strong> of Nuclear Facilities Decommissi<strong>on</strong>ing in Japan<br />
Yusuke Masuda, Yukihiro Iguchi, Satoru Kawasaki, Masami Kato, JNES (Japan)<br />
In Japan, 4 nuclear power stati<strong>on</strong>s are under decommissi<strong>on</strong>ing and some nuclear fuel cycle facilities are expected to<br />
be decommissi<strong>on</strong>ed in the future. On the other hand, the safety regulati<strong>on</strong> of decommissi<strong>on</strong>ing of nuclear facilities was<br />
changed by amending law in 2005. An approval system after review process of decommissi<strong>on</strong>ing plan was adopted and<br />
applied to the power stati<strong>on</strong>s above. In this situati<strong>on</strong>, based <strong>on</strong> the experiences of the new regulatory system, the system<br />
should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety<br />
Agency (NISA) is in charge of regulati<strong>on</strong> of commercial nuclear facilities in Japan and decommissi<strong>on</strong>ing of them is<br />
included. Japan Nuclear Energy Safety Organizati<strong>on</strong> (JNES) is in charge of technical supports for NISA as a TSO<br />
(Technical Support Organizati<strong>on</strong>) also in this field. As for decommissi<strong>on</strong>ing, based <strong>on</strong> the needs in terms of regulati<strong>on</strong>,<br />
JNES has been c<strong>on</strong>tinuing research activities from October 2003, when JNES has been established. C<strong>on</strong>sidering the<br />
“Prioritized Nuclear Safety Research Plan (August 2009)” of the Nuclear Safety Commissi<strong>on</strong> of Japan and the situati<strong>on</strong><br />
of operators facilities, “Regulatory Support Research Plan between FY 2010-2014” was established in November 2009,<br />
which shows the present regulatory needs and a research program. This program c<strong>on</strong>sists of researches for 1. review<br />
process of decommissi<strong>on</strong>ing plan of power reactors, 2. review process of decommissi<strong>on</strong>ing plan of nuclear fuel cycle<br />
facilities, 3. terminati<strong>on</strong> of license at the end of decommissi<strong>on</strong>ing and 4. management of decommissi<strong>on</strong>ing waste. For the<br />
item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust<br />
diffusi<strong>on</strong> and risk assessment during decommissi<strong>on</strong>ing, which are useful findings for the review process. For the item 2,<br />
safety requirements for the decommissi<strong>on</strong>ing of nuclear fuel cycle facilities was compiled, which will be used in the<br />
future review. For the item 3, measuring method, release procedure and analysis code for the site release were studied for<br />
the establishment of the license terminati<strong>on</strong> process in the future. From FY 2010, based <strong>on</strong> the new plan, we have started<br />
the researches for the standardizati<strong>on</strong> of review process of decommissi<strong>on</strong>ing plan for power reactors and nuclear fuel<br />
cycle facilities, establishing the process and criteria of license terminati<strong>on</strong> and appropriate method of management of<br />
decommissi<strong>on</strong>ing waste based <strong>on</strong> the waste form c<strong>on</strong>firmati<strong>on</strong> process.<br />
3) 40136 – Decommissi<strong>on</strong>ing Costing Approach Based <strong>on</strong> the Standardised List of Costing Items; Less<strong>on</strong>s<br />
Learnt<br />
Vladimir Daniska, Frantisek Ondra, Peter Bezak, DECONTA, a.s. (Slovakia);<br />
Ivan Rehak, Marek Vasko, Jozef Pritrsky, DECOM a.s. (Slovakia) ;<br />
Matej Zachar, Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> document “A Proposed Standardised List of Items for Costing Purposes” was issues in 1999 by OECD/NEA,<br />
IAEA and European Commissi<strong>on</strong> for promoting the harm<strong>on</strong>isati<strong>on</strong> in decommissi<strong>on</strong>ing costing. It is a systematic list of<br />
typical decommissi<strong>on</strong>ing activities classified into chapters 01 to 11 with three hierarchical numbered levels. Cost groups<br />
are defined in chapter 12 for presenting cost for each activity. In this way the document is the standardised matrix of<br />
decommissi<strong>on</strong>ing activities and cost groups with unambiguous meaning of items. Knowing what is behind the items of<br />
the standardised cost structure makes the comparis<strong>on</strong> of cost for various decommissi<strong>on</strong>ing projects transparent. <str<strong>on</strong>g>The</str<strong>on</strong>g>re are<br />
two principal approaches for use of the standardised cost structure. First approach c<strong>on</strong>verts the cost items from specific<br />
cost structures into the standardised cost structure for the purpose of cost presentati<strong>on</strong>. Sec<strong>on</strong>d approach uses the<br />
extended standardised cost structure as the calculati<strong>on</strong> structure; the cost data have the standardised format directly.<br />
Several advantages can be identified in this approach. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper presents general aspects of the costing methodology<br />
based <strong>on</strong> the standardised cost structure and less<strong>on</strong>s learnt from last ten years of implementati<strong>on</strong> of the standardised cost<br />
structure as the cost calculati<strong>on</strong> structure in the computer code OMEGA. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper presents following aspects:<br />
• general principles of decommissi<strong>on</strong>ing costing in current costing methodologies based <strong>on</strong> informati<strong>on</strong> <strong>on</strong> costing<br />
methodologies available,<br />
• standardised cost structure, methods of its use in costing, cost calculati<strong>on</strong> structures based <strong>on</strong> the standardised<br />
cost structure,<br />
• principles of cost calculati<strong>on</strong> methodology based <strong>on</strong> the standardised cost structure, input data for the<br />
methodology, cost calculati<strong>on</strong> process, management of calculated data<br />
• interacti<strong>on</strong>s of main cost structures involved in standardised costing: standardised cost calculati<strong>on</strong> structure,<br />
work breakdown structure of a decommissi<strong>on</strong>ing project, relati<strong>on</strong>s to cost accounting structures<br />
• main features of the computer code OMEGA: implementati<strong>on</strong> of the standardised cost structure as the cost<br />
calculati<strong>on</strong> structure, management of the material and radioactivity flow in the decommissi<strong>on</strong>ing process,<br />
generati<strong>on</strong> of Gantt charts for managing of the decommissi<strong>on</strong>ing projects, data feedback from real processes,<br />
links to cost accounting systems<br />
• internati<strong>on</strong>al activities for promoting of the standardised cost structure and for its upgradin<br />
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Abstracts<br />
4) 40290 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Outline of Decommissi<strong>on</strong>ing Plan for Hamaoka Nuclear Power Stati<strong>on</strong> Unit-1 and Unit-2<br />
Yoshifusa Fukuoka, Chubu Electric Power Co., Inc. (Japan)<br />
Hamaoka Nuclear Power Stati<strong>on</strong>'s Unit-1 and Unit-2 ended their operati<strong>on</strong> <strong>on</strong> January 30, 2009. <str<strong>on</strong>g>The</str<strong>on</strong>g> Unit-1 and 2<br />
will be dismantled and removed, and doing this requires establishing a nuclear reactor facility decommissi<strong>on</strong>ing plan, and<br />
getting the approval of the nati<strong>on</strong>al government. <str<strong>on</strong>g>The</str<strong>on</strong>g>ir decommissi<strong>on</strong>ing procedure commenced after the submissi<strong>on</strong> of<br />
the "Applicati<strong>on</strong> for the approval of the decommissi<strong>on</strong>ing plan for Hamaoka Nuclear Power Stati<strong>on</strong> Unit-1 and 2" to the<br />
Minister of Ec<strong>on</strong>omy, Trade and Industry <strong>on</strong> June 1, 2009 , and subsequent approval for the applicati<strong>on</strong> <strong>on</strong> November 18,<br />
2009. ?<str<strong>on</strong>g>The</str<strong>on</strong>g> applicati<strong>on</strong> includes an overall plan for dismantling reactor facilities safely and surely, a descripti<strong>on</strong> of tasks<br />
to be performed during the period Chubu Electric is preparing to dismantle the facilities in the coming years and safety<br />
assurance measures, am<strong>on</strong>g other informati<strong>on</strong>. ?According to the plan, the decommissi<strong>on</strong>ing of Unit-1 and Unit-2 is to be<br />
completed by the end of FY2036. <str<strong>on</strong>g>The</str<strong>on</strong>g> 28-year schedule is divided into four phases. ?Phase 1?Preparati<strong>on</strong> Stage,<br />
FY2009 ? FY2014 Transporting and transferring nuclear fuel out of the plants, investigating the status of c<strong>on</strong>taminati<strong>on</strong>,<br />
c<strong>on</strong>ducting system dec<strong>on</strong>taminati<strong>on</strong>, and dismantling / removing facilities and equipment outside RCA ?Phase<br />
2?Dismantling and Removal Stage for Reactor Z<strong>on</strong>e Peripheral Facilities, FY2015 ? FY2022 Dismantling / removing<br />
reactor z<strong>on</strong>e peripheral facilities, safely storing dismantlement debris, and installing facilities for processing<br />
dismantlement debris ? Phase 3?Dismantling and Removal Stage for Reactor Z<strong>on</strong>es, FY2023 ? FY2029 Dismantling and<br />
removing the reactor z<strong>on</strong>e (covering the reactor vessel, core support structures, and radiati<strong>on</strong> shields surrounding the<br />
reactor vessel) ?Phase 4?Dismantling and Removal Stage for Building Structures, FY2030 ? FY2036 Removing<br />
radioactive materials inside plant buildings, and dismantling / removing the buildings.<br />
Of waste to be generated in decommissi<strong>on</strong>ing work at Unit-1 and Unit-2, low-level radioactive waste accounts for<br />
approx. 17,000 t<strong>on</strong>s . Low-level radioactive waste is sorted according to the types of radioactive substances c<strong>on</strong>tained or<br />
the level of radiati<strong>on</strong> based <strong>on</strong> laws and regulati<strong>on</strong>s, and appropriately put to underground disposal based <strong>on</strong> the<br />
classificati<strong>on</strong>s. Specific methods for disposal, including the disposal site, will be decided before the start of<br />
dismantlement work <strong>on</strong> reactor z<strong>on</strong>e's peripheral facilities, and reflected to the decommissi<strong>on</strong>ing plan for approval.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> decommissi<strong>on</strong>ing plan for Hamaoka Nuclear Power Stati<strong>on</strong> Unit-1 and Unit-2 represents Japan's first<br />
decommissi<strong>on</strong>ing of a commercial light-water nuclear power plant. <str<strong>on</strong>g>The</str<strong>on</strong>g> priority is given to safety to steadily implement<br />
the decommissi<strong>on</strong>ing plan with transparency <strong>on</strong> Hamaoka NPS, and to acquisiti<strong>on</strong> of the trust from every<strong>on</strong>e c<strong>on</strong>cerned.<br />
5) 40015 – Study <strong>on</strong> Influence of Nuclear Fuel Material Management and Transfer Scenarios <strong>on</strong><br />
Decommissi<strong>on</strong>ing<br />
Kazuma Mizukoshi, Nuclear Engineering, Ltd. (Japan)<br />
1. Summary <str<strong>on</strong>g>The</str<strong>on</strong>g> Japanese electric utilities are required to prepare plans to transfer its nuclear fuel material by the<br />
end of the decommissi<strong>on</strong>ing period. <str<strong>on</strong>g>The</str<strong>on</strong>g>re can be several scenarios regarding the management and transfer of nuclear<br />
fuel material. It is necessary to fully understand the characteristics of individual scenarios so that the most suitable<br />
method can be selected according to the c<strong>on</strong>diti<strong>on</strong>s specific to each plant. We have examined how the nuclear fuel<br />
material management and transfer scenarios cause influences <strong>on</strong> the decommissi<strong>on</strong>ing and evaluated the characteristics<br />
(advantages and disadvantages) of each scenario. We expect that the result of this study will be useful for a nuclear<br />
power stati<strong>on</strong> which plans decommissi<strong>on</strong>ing to choose a suitable and effective scenario for the nuclear fuel material<br />
management and transfer.<br />
2. Method We collected informati<strong>on</strong> about methods of nuclear fuel material management and transfer and extracted<br />
several scenarios as shown below: Scenario A? Spent fuel (SF) is transported to a reprocessing plant after storing it in the<br />
same SFP as it was stored during the in-service period. Scenario B? SF is transported to an another unit of the same<br />
power stati<strong>on</strong> to transfer the management of the SF to the unit. ?<str<strong>on</strong>g>The</str<strong>on</strong>g> transportati<strong>on</strong> between units.? Scenario C? SF is<br />
transported to an interim storage facility to transfer the management of SF to the interim storage facility. Scenario D: SF<br />
is transported to a reprocessing plant after storing it in a SFP which is isolated by replacing existing system comp<strong>on</strong>ents<br />
with temporarily installed comp<strong>on</strong>ents. Scenario E?SF is transported to an interim storage facility after storing it in a SFP<br />
which is isolated by replacing existing system comp<strong>on</strong>ents with temporarily installed comp<strong>on</strong>ents, and its management is<br />
transferred to the interim storage facility.<br />
Regarding the scenarios menti<strong>on</strong>ed above, we examined the influence <strong>on</strong> decommissi<strong>on</strong>ing c<strong>on</strong>diti<strong>on</strong>s (dismantling<br />
/ storage areas, and so <strong>on</strong>), decommissi<strong>on</strong>ing process, and costs.<br />
3. Result A study <strong>on</strong> the influence of the scenarios of nuclear fuel material management and transfer <strong>on</strong><br />
decommissi<strong>on</strong>ing has clarified the characteristics (advantages and disadvantages) of individual scenarios and which<br />
scenario is suitable to specific c<strong>on</strong>diti<strong>on</strong>s.<br />
4. C<strong>on</strong>clusi<strong>on</strong> We could fully understand the characteristics of the scenarios of nuclear fuel material management<br />
and transfer. We expect the result obtained from this study will be useful for a nuclear power plant to choose a suitable<br />
scenario of nuclear fuel material management and transfer.<br />
6) 40100 – Dose Assessment for setting of EPZ in Emergency Plan for Decommissi<strong>on</strong>ing of Nuclear Power Plant<br />
Hirokazu Minato, Hitachi-GE Nuclear Energy (Japan); Takatoshi Hattori, CRIEPI (Japan);<br />
Toshihiko Higashi,<str<strong>on</strong>g>The</str<strong>on</strong>g> Kansai Electric Power Co., Inc. (Japan); Takehiro Iwata, JAPC (Japan)<br />
In emergency plan for a nuclear power plant, taking enough measures in EPZ boundary (Emergency Planning Z<strong>on</strong>e)<br />
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Abstracts<br />
is <strong>on</strong>e of priority matters, to have protecti<strong>on</strong> against the release of radioactive materials in accident efficiently and<br />
quickly to minimize envir<strong>on</strong>mental impacts. EPZ is set as the z<strong>on</strong>e which emergency plans should be mainly prepared <strong>on</strong><br />
emergency c<strong>on</strong>diti<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> criteria of EPZ is that dose value in the area between plant and EPZ boundary have to be less<br />
than 10mSv, even if very c<strong>on</strong>servative release mechanisms and path are supposed. <str<strong>on</strong>g>The</str<strong>on</strong>g> released amount of radioactive<br />
material from a nuclear power plant is calculated to the accident scenario were supposed with the each phase of<br />
decommissi<strong>on</strong>ing. Moreover, the dose value is calculated as the evaluati<strong>on</strong> of envir<strong>on</strong>mental impacts, using atmospheric<br />
diffusi<strong>on</strong> parameters are determined by the plume c<strong>on</strong>centrati<strong>on</strong> gaussian type distributi<strong>on</strong> model at steady state, and<br />
annual meteorological data of the reference plants. Both of 'the spent fuel storage phase' and 'the safe maintenance and<br />
dismantling phase' <strong>on</strong> each of the expected accident scenario, the dose value in EPZ boundary is much less than safety<br />
criteria (10mSv), and there is no need to plan offsite emergency plan, such as the Sheltering and Escape for a reference<br />
plant. This result is agreeing with the opini<strong>on</strong> of Waste and decommissi<strong>on</strong> working group 2006 of Western European<br />
Nuclear Regulator's Associati<strong>on</strong> (WENRA).<br />
7) 40044 – Decommissi<strong>on</strong>ing of Ignalina NPP<br />
Karolis Zemkajus, Algirdas Vaidotas, Radioactive Waste Management Agency in Lithuania (Lithuania)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper describes the preparati<strong>on</strong> for the decommissi<strong>on</strong>ing and implementati<strong>on</strong> of the Programme <strong>on</strong> Ignalina<br />
NPP decommissi<strong>on</strong>ing. Emphasis is given to the Final Decommissi<strong>on</strong>ing Plan, the whole INPP decommissi<strong>on</strong>ing process,<br />
Radiati<strong>on</strong> Protecti<strong>on</strong> Programme, waste to be processed and disposed. Ignalina NPP was designed and c<strong>on</strong>structed (Unit<br />
1 was commissi<strong>on</strong>ed in 1983, Unit 2 was commissi<strong>on</strong>ed in 1987) at the time when safety culture was not the issue<br />
addressed in a special way. <str<strong>on</strong>g>The</str<strong>on</strong>g> opini<strong>on</strong> of the internati<strong>on</strong>al community was very important to Lithuania as it was striving<br />
for the membership of the European Uni<strong>on</strong> and NATO. Thus, Lithuania, respecting the opini<strong>on</strong> of the internati<strong>on</strong>al<br />
community, and pursuant to the Nuclear Safety Account Grant Agreement, envisaged shutdown of Unit 1of Ignalina NPP<br />
by year 2005 in the Nati<strong>on</strong>al energy strategy ratified by the Seimas in 1999, c<strong>on</strong>sidering the l<strong>on</strong>g-term and essential<br />
financial assistance c<strong>on</strong>diti<strong>on</strong>s ensured by the EU, G-7 countries and other internati<strong>on</strong>al instituti<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> Nati<strong>on</strong>al energy<br />
strategy updated in year 2002 states that having in mind that the European Uni<strong>on</strong> countries acknowledged INPP<br />
decommissi<strong>on</strong>ing to be an excepti<strong>on</strong>al financial burden for Lithuania, as well as a process which exceeds current<br />
financial perspectives of the country, Unit 2 will be shutdown in 2009 if sufficient financial resources supported by<br />
agreements with the EU instituti<strong>on</strong>s and other d<strong>on</strong>ors are in place. Regarding the preparati<strong>on</strong> for the decommissi<strong>on</strong>ing<br />
and implementati<strong>on</strong> of the Programme <strong>on</strong> INPP Unit 1 decommissi<strong>on</strong>ing during the period 2001-2004 Ignalina NPP<br />
developed and the Ministry of Ec<strong>on</strong>omy approved the Final Decommissi<strong>on</strong>ing Plan (FDP) in 2005. This Plan covers the<br />
whole INPP decommissi<strong>on</strong>ing process (both Units, auxiliary facilities and eventually the interim spent fuel and waste<br />
storage facilities). Decommissi<strong>on</strong>ing activities and projects are planned <strong>on</strong> the basis of the herein proposed strategy.<br />
Generally, FDP describes principles, methods and techniques and the overall plans and schedules required to ensure<br />
radiological safe, envir<strong>on</strong>mental friendly and ec<strong>on</strong>omic decommissi<strong>on</strong>ing of the INPP. In summary, the following<br />
informati<strong>on</strong> is provided in FDP: • applied regulatory framework; • adopted dismantling strategy; • plan and schedule of<br />
decommissi<strong>on</strong>ing; • radioactive and hazardous material inventories; • decommissi<strong>on</strong>ing activities; • dec<strong>on</strong>taminati<strong>on</strong><br />
activities; • dismantling tools and methods; • INPP waste management strategy; • safety and envir<strong>on</strong>mental impact<br />
assessment; • Radiati<strong>on</strong> Protecti<strong>on</strong> Programme; • INPP organizati<strong>on</strong> performing decommissi<strong>on</strong>ing; • decommissi<strong>on</strong>ing<br />
costs and funding; • quality assurance; • final radiati<strong>on</strong> survey and facility and site restorati<strong>on</strong>. From the nuclear safety<br />
standpoint, the activities related to potential risk will be performed during the first 10 years following the reactor final<br />
shutdown (spent fuel handling, dec<strong>on</strong>taminati<strong>on</strong>, systems modificati<strong>on</strong>s and isolati<strong>on</strong> etc.). Works will be prepared and<br />
carried out by the skilled INPP staff. According the Programme <strong>on</strong> Ignalina NPP decommissi<strong>on</strong>ing the Schedule of<br />
Decommissi<strong>on</strong>ing: • units final shutdown: unit 1 – 31/12/2004, unit 2 – 31/12/2009; • reactors defuelling: unit 1 –<br />
31/12/2009, unit 2 – 28/02/2012; • pools defuelling: unit 1 – 31/08/2015, unit 2 – 12/01/2016; • start D&D activities: unit<br />
1 – middle 2010, unit 2 – early 2012. FDP describes volumes of unc<strong>on</strong>diti<strong>on</strong>ed waste to be c<strong>on</strong>sidered while preparing<br />
for and performing the decommissi<strong>on</strong>ing. In summarizing, it could be stated that INPP operati<strong>on</strong> and decommissi<strong>on</strong>ing<br />
will generate approximately 5 900m3 of spent resins, perlite and sediments and about 130 000m3 of solid radioactive<br />
waste. <str<strong>on</strong>g>The</str<strong>on</strong>g> operati<strong>on</strong>al stored waste estimates by end 2009: • spent Fuel - 23000 assemblies; • solid Waste - 30000 m3; •<br />
bituminized waste - 14000 m3; • waste to be cemented (resins, perlites) - 6000 m3 (retrieval and cementati<strong>on</strong> <strong>on</strong>-going<br />
since 2005). <str<strong>on</strong>g>The</str<strong>on</strong>g> Decommissi<strong>on</strong>ing waste estimates: • spent fuel -18000 assemblies; • equipment - 130000 t<strong>on</strong>s of steel; •<br />
reactor - 4000 t<strong>on</strong>s of steel, 4000 t<strong>on</strong>s graphite; • buildings - 1000000 m3 of c<strong>on</strong>crete, 200000 t<strong>on</strong>s of steel. This waste<br />
will require processing in the new cementati<strong>on</strong> facility and future solid waste management After dec<strong>on</strong>taminati<strong>on</strong> of the<br />
emptied INPP facilities, final demoliti<strong>on</strong> of the building structures will additi<strong>on</strong>ally generate some 965000 m3 of<br />
c<strong>on</strong>crete and 190000 t<strong>on</strong>s of steel to be free released.<br />
SESSION G1 : <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Collaborati<strong>on</strong><br />
1) 40118 – Advancing the Use of IAEA Networks in Radioactive Waste Management: Past Successes, Present<br />
Challenges and Future Opportunities<br />
Paul Degnan, John Kinker, Irena Mele, Paul J. Dinner, Horst M<strong>on</strong>ken Fernandes,<br />
Ant<strong>on</strong>io Morales, Lumir Nachmilner, Shaheed Hossain, IAEA<br />
65
Abstracts<br />
Since 2001 the <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy Agency has champi<strong>on</strong>ed the c<strong>on</strong>cept and use of Networks to advance<br />
radioactive waste management across the globe. At the present time there are four Networks managed <strong>on</strong> behalf of<br />
Member States by the IAEA and a fifth <strong>on</strong>e is currently being implemented. <str<strong>on</strong>g>The</str<strong>on</strong>g> scopes of interest covered by the<br />
Networks encompass near-surface and deep geological disposal, the decommissi<strong>on</strong>ing of nuclear facilities, the<br />
envir<strong>on</strong>mental remediati<strong>on</strong> of sites c<strong>on</strong>taminated with radioactive materials and the characterisati<strong>on</strong> of low- and<br />
intermediate-level radioactive wastes. To date over 100 organisati<strong>on</strong>s from more than 40 Member States are involved in<br />
the Networks. Many of these Network participants generously d<strong>on</strong>ate resources, time and effort to support Network<br />
activities, while others with nascent or otherwise less well developed programmes are still in the process of acquiring<br />
experience, capabilities and know-how. Regardless of the stage of development, all Network participants share in the<br />
mutual benefits that arise from improved communicati<strong>on</strong>s with sister organisati<strong>on</strong>s and the sharing of experience and<br />
knowledge. <str<strong>on</strong>g>The</str<strong>on</strong>g> universal Goal of the Networks is the promoti<strong>on</strong> of methods and technologies that will enhance the<br />
safety and sustainability of radioactive waste management practices and facilities. This Goal is being achieved through<br />
c<strong>on</strong>tinuous improvements in communicati<strong>on</strong> and knowledge sharing between Network participants and the provisi<strong>on</strong> of<br />
enhanced opportunities for training, involvement in dem<strong>on</strong>strati<strong>on</strong> projects and the development of novel technologies<br />
and methodologies. We recognise that interdisciplinary understanding and the coordinati<strong>on</strong> of efforts at key interfaces at<br />
the back-end of the fuel cycle are critical aspects for achieving the Network Goal efficiently and effectively.<br />
C<strong>on</strong>sequently, the IAEA Networks that will be operati<strong>on</strong>al by the end of 2010 are themselves are being molded into an<br />
organic “Network of Networks” where the use of new electr<strong>on</strong>ic media and the possibilities presented by enhanced<br />
communicati<strong>on</strong> channels will be exploited. Here we provide an overview of the IAEA Networks in radioactive waste<br />
management and present a new tool that is under development, an internet-based portal for enhanced communicati<strong>on</strong>s<br />
and the provisi<strong>on</strong> of improved training opportunities.<br />
2) 40287 – <str<strong>on</strong>g>The</str<strong>on</strong>g> activities of the OECD/NEA RWMC in the Field of HLW and SF disposal<br />
Claudio Pescatore, OECD/NEA<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> OEDCD/NEA seeks to assist its member countries in developing strategies for the management of all types of<br />
radioactive material, including waste, that are safe and sustainable and that meet the broad needs of society - with<br />
particular emphasis <strong>on</strong> the management of l<strong>on</strong>g-lived waste and spent fuel and <strong>on</strong> decommissi<strong>on</strong>ing of disused nuclear<br />
facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g> programme of work in the area of radioactive waste management is supervised by the Radioactive Waste<br />
Management Committee (RWMC) made of senior representatives from regulatory authorities, radioactive waste<br />
management and decommissi<strong>on</strong>ing organisati<strong>on</strong>s, policy making bodies, and research-and-development instituti<strong>on</strong>s from<br />
the NEA countries. <str<strong>on</strong>g>The</str<strong>on</strong>g> IAEA participates in the work of the committee, and the European Commissi<strong>on</strong> (EC) is a full<br />
member. Str<strong>on</strong>g ties are maintained with nati<strong>on</strong>al high-level advisory bodies to governments and with internati<strong>on</strong>al<br />
bodies such as the <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Committee <strong>on</strong> Radiati<strong>on</strong> Protecti<strong>on</strong>. RWMC helps the nati<strong>on</strong>al programmes through a<br />
broad programme of work that: fosters a shared and broad-based understanding of the state of the art and emerging<br />
issues; facilitates the elaborati<strong>on</strong> of waste management strategies that respect societal requirements; helps to provide<br />
comm<strong>on</strong> bases to the nati<strong>on</strong>al regulatory frameworks; enables the management of radioactive waste and materials to<br />
benefit from progress of scientific and technical knowledge; c<strong>on</strong>tributes to knowledge c<strong>on</strong>solidati<strong>on</strong> and transfer, e.g.,<br />
through the organizati<strong>on</strong> of specialist meetings and publicati<strong>on</strong> of technical reports, c<strong>on</strong>sensus statements and short<br />
flyers; and helps advance the state of the art, e.g., by providing a framework for the c<strong>on</strong>duct of internati<strong>on</strong>al peer reviews.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> latest collective statement of the RWMC dates to 2008 <strong>on</strong> “moving forward with geological disposal of radioactive<br />
waste”; the latest peer review was of the French Dossier 2005. A new peer review of the safety report for a spent fuel<br />
repository in Sweden is being organised. <str<strong>on</strong>g>The</str<strong>on</strong>g> RWMC holds multi-stakeholder, nati<strong>on</strong>al workshops. <str<strong>on</strong>g>The</str<strong>on</strong>g> latest (2009) was<br />
in France, in the siting regi<strong>on</strong> for the nati<strong>on</strong>al HLW repository. <str<strong>on</strong>g>The</str<strong>on</strong>g> RWMC manages a database of country informati<strong>on</strong>,<br />
in the form of a country reports and country profiles updated yearly; a summary of the regulatory infrastructure in NEA<br />
countries is also maintained. Current work areas include: promoting greater understanding of radioactive waste<br />
management and decommissi<strong>on</strong>ing disciplines; an internati<strong>on</strong>al project <strong>on</strong> the topic of “retrievability and reversibility”;<br />
assisting the organisati<strong>on</strong> of an “<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> <strong>on</strong> Geological Repositories” in Japan in 2011; initiating<br />
dialogue with ICRP with a view to updating the ICRP guidance in the field of geological disposal; starting a project in<br />
the field of informati<strong>on</strong> and memory keeping. Specific technical areas also include optimizati<strong>on</strong>, treatment of the very<br />
l<strong>on</strong>g time scales, assessing the state of the art in safety assessment methods, and the operati<strong>on</strong> phase of repositories. An<br />
overview is provided of these activities and the relevant issues.<br />
3) 40147 – Grimsel Test Site - Phase VI Status and Outlook<br />
Ingo Blechschmidt, Sven Peter Teodori, Stratis Vomvoris, Nagra (Switzerland)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Grimsel Test Site (GTS) (www.grimsel.com) is a generic underground research laboratory located in the<br />
crystalline rocks of the Aare Massif of the Swiss Alps and is owned and operated by the Nati<strong>on</strong>al Cooperative for the<br />
Disposal of Radioactive Waste (Nagra). <str<strong>on</strong>g>The</str<strong>on</strong>g> GTS is unique in that it includes a class B/C c<strong>on</strong>trol z<strong>on</strong>e in which<br />
repository relevant radi<strong>on</strong>uclides can be used as tracers of rock processes. 2009 marked the 25th year of GTS’s operati<strong>on</strong><br />
and the current running Phase VI is planned until 2013. Experiments have evolved from those focused <strong>on</strong> characterising<br />
the structural geology, groundwater geochemistry and hydrogeology of the test site during the 80s; to radi<strong>on</strong>uclide<br />
migrati<strong>on</strong> experiments in the 90s; and then more recently to assessing perturbati<strong>on</strong> effects of repository implementati<strong>on</strong><br />
and dem<strong>on</strong>strating engineering and operati<strong>on</strong>al aspects of the repository system for the last 10 years.<br />
66
Abstracts<br />
Currently over 25 internati<strong>on</strong>al organisati<strong>on</strong>s participate in various projects at the GTS. On-going internati<strong>on</strong>al<br />
partner projects are as follows: evaluati<strong>on</strong> of full-scale engineered systems under simulated heat producti<strong>on</strong> and<br />
l<strong>on</strong>g-term natural saturati<strong>on</strong> (FEBEXe); emplacement of a shotcrete low-pH plug (EC Project ESDRED); testing and<br />
evaluati<strong>on</strong> of standard m<strong>on</strong>itoring techniques (TEM/MoDeRn) including both wired and n<strong>on</strong>-wired techniques;<br />
l<strong>on</strong>g-term cement studies (LCS) which aims at improving the understanding of low-pH cement interacti<strong>on</strong> effects in<br />
water c<strong>on</strong>ducting features; the Colloid Formati<strong>on</strong> and Migrati<strong>on</strong> Project (CFM) which focuses <strong>on</strong> colloid generati<strong>on</strong> and<br />
migrati<strong>on</strong> from a bent<strong>on</strong>ite source doped with radi<strong>on</strong>uclides; and the L<strong>on</strong>g-Term Diffusi<strong>on</strong> (LTD) project which aims at<br />
in-situ verificati<strong>on</strong> of l<strong>on</strong>g term diffusi<strong>on</strong> c<strong>on</strong>cepts for radi<strong>on</strong>uclides.<br />
Additi<strong>on</strong>al experiments include techniques for determinati<strong>on</strong> of fracture network hydraulic and migrati<strong>on</strong><br />
parameters and behaviour of grouting materials. New large-scale experiments to test the emplacement techniques and<br />
behaviour seals/plugs at 1:1 scale, under hydraulic pressure differential of up to 50 bars with parallel migrati<strong>on</strong> of<br />
repository-generated gas are in the planning stage.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> status of the <strong>on</strong>-going experiments as well as the future plans and possibilities for new partners are summarised<br />
in this poster presentati<strong>on</strong>.<br />
SESSION L4: Solidificati<strong>on</strong> and Package (2)<br />
1) 40299 – Treatment of low level radioactive waste by plasma: a proven technology?<br />
Jan Deckers, Belgoprocess, NV (Belgium)<br />
Introducti<strong>on</strong> Large amounts of actual and historical low level radioactive waste, with varying characteristics, are<br />
stored and generated from the operati<strong>on</strong> and maintenance of nuclear power plants, the nuclear fuel cycle, research<br />
laboratories, pharmaceutical and medical facilities. Virtual all of these waste streams can be treated by the plasma<br />
technology resulting in a final product free from organics, liquids and moisture, and meets without a doubt the<br />
acceptance criteria for safe storage and disposal.<br />
Review <str<strong>on</strong>g>The</str<strong>on</strong>g> plasma is a highly desirable heat source. Its high temperature of up to 10,000 °C can treat the<br />
radioactive waste as is. <str<strong>on</strong>g>The</str<strong>on</strong>g> inorganic materials are melted into a glassy slag, c<strong>on</strong>taining most of the radioactive isotopes<br />
while the organic material are vaporised into a syngas and afterwards oxidised in an afterburner. This technology is very<br />
suitable for historical waste c<strong>on</strong>taining mixtures of inorganic, organic, liquids, sludge, etc, with almost no preparati<strong>on</strong> of<br />
the waste and minimum risks for radioactive c<strong>on</strong>taminati<strong>on</strong> and exposure.<br />
Discussi<strong>on</strong> In the interest of the waste producers and future generati<strong>on</strong>s, a high volume reducti<strong>on</strong> factor (VRF) of<br />
the waste is desired in order to minimise the volume and overall costs of storage and waste disposal. Not <strong>on</strong>ly the VRF is<br />
of importance but also the growing requirements for improved quality of the final waste form. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore the plasma<br />
technology can also be used to rec<strong>on</strong>diti<strong>on</strong> previous c<strong>on</strong>diti<strong>on</strong>ed waste packages that no l<strong>on</strong>ger meet the current<br />
acceptance criteria for final disposal.<br />
C<strong>on</strong>clusi<strong>on</strong> This paper describes in detail the principles of plasma, the different waste feed systems, off gas<br />
treatment, operati<strong>on</strong>al experience and future plasma plants.<br />
2) 40128 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Zwilag Plasma Facility - Five Years of Successful Operati<strong>on</strong><br />
Walter Heep, Zwilag Interim Storage Facility (Switzerland)<br />
This paper is about a treatment facility of low level radioactive wastes that operates with plasma technology.<str<strong>on</strong>g>The</str<strong>on</strong>g><br />
first processing of low level radioctive wastes from Swiss nuclear power plants marked the successful completi<strong>on</strong> of the<br />
commissi<strong>on</strong>ing of this facility in March 2004. <str<strong>on</strong>g>The</str<strong>on</strong>g> commercial operati<strong>on</strong> of the plasma plant owned by Zwilag<br />
Zwischenlager Würenlingen AG (Zwilag) has also enabled this technology to be used successfully for the first time in the<br />
nuclear field in a way that addresses the issue of radiati<strong>on</strong> protecti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> plasma facility has been operating now for five<br />
years and was granted an unrestricted operating license in September 2009.<br />
3) 40293 – Safety Assessment of Disposal C<strong>on</strong>tainer for Higher Activity Low Level Waste<br />
Mot<strong>on</strong>ori Nakagami, Seiji Komatsuki, Chubu Electric Power Co., Inc. (Japan);<br />
Kyosuke Fujisawa, Takashi Nishio, KOBE STEEL, LTD. (Japan);<br />
Thomas Quercetti, André Musolff, Karsten Müller,<br />
Federal Institute for Materials Research and Testing (Germany)<br />
As <strong>on</strong>e of the studies <strong>on</strong> "yoyushindo disposal" whose c<strong>on</strong>cept is similar to an intermediate disposal, the<br />
development of a disposal c<strong>on</strong>tainer has been c<strong>on</strong>ducted by the Federati<strong>on</strong> of Electric Power Companies of Japan. To<br />
assess a drop event of a waste package in which stored the radioactive wastes from nuclear power plants, the toughness<br />
of the disposal c<strong>on</strong>tainer was evaluated by drop tests using three specimens which have actual dimensi<strong>on</strong>s, drop analysis,<br />
fracture mechanics assessment and macroscopic tests. <str<strong>on</strong>g>The</str<strong>on</strong>g> three specimens for drop tests were manufactured in<br />
c<strong>on</strong>siderati<strong>on</strong> of the design specificati<strong>on</strong>s and the manufacture operati<strong>on</strong>s in nuclear power plants. <str<strong>on</strong>g>The</str<strong>on</strong>g> lid plates of the<br />
67
Abstracts<br />
specimens were welded to the body plates without pre- and post-weld heat treatment by using a remote automated<br />
welding machine. <str<strong>on</strong>g>The</str<strong>on</strong>g> drop tests showed that no penetrati<strong>on</strong> cracks or splash of its c<strong>on</strong>tent occurred in the disposal<br />
c<strong>on</strong>tainer under c<strong>on</strong>servative c<strong>on</strong>diti<strong>on</strong>s such as the maximum weight and height in the handling. Drop analysis and the<br />
fracture mechanics assessment indicate that the strain induced by the drop impact did not exceed the fracture strain and<br />
an unstable fracture did not occur. And macroscopic tests showed that penetrati<strong>on</strong> cracks did not occur at 8m drop events.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se tests and evaluati<strong>on</strong>s c<strong>on</strong>firmed that the disposal c<strong>on</strong>tainer had sufficient toughness.<br />
SESSION L5: Recycling and Clearance<br />
1)� 40223 – NPP Bulk Equipment Dismantling Problems and Experience<br />
Alexander B.Gelbutovsky, Eugeny V. Balushkin, Jury A. Epikhin,<br />
Alexander V. Troshev, Peter I. Cheremisin, ECOMET-S JSC (Russia)<br />
NPP bulk equipment dismantling problems and experience are summarized. “ECOMET-S” JSC is shown as <strong>on</strong>e of<br />
the companies which are able to make NPPs industrial sites free from stored bulk equipment with its further utilizati<strong>on</strong>.<br />
“ECOMET-S” JSC is the Russian Federati<strong>on</strong> sole specialized metallic LLW (MLLW) treatment and utilizati<strong>on</strong> facility.<br />
Company/s main objectives are waste predisposal volume reducti<strong>on</strong> and treatment for the unrestricted release as a scrap.<br />
Leningrad NPP decommissi<strong>on</strong>ed main pumps and moisture separators / steam super heaters dismantling results are<br />
presented. Prospective fragmentati<strong>on</strong> technologies (diam<strong>on</strong>d and electro-erosive cutting) testing results are described.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> electro-erosive cutting machine designed by “ECOMET-S” JSC is presented. <str<strong>on</strong>g>The</str<strong>on</strong>g> fragmentati<strong>on</strong> technologies<br />
implementati<strong>on</strong> plans for nuclear industry are presented too. Key words: cutting, fragmentati<strong>on</strong>, NPP bulk equipment,<br />
recycling, utilizati<strong>on</strong>, main pump casing, gas cutting, melting, metal ingots, unrestricted use, separator, steam super<br />
heater, air plasma cutting machine, diam<strong>on</strong>d cutting, electro erosive cutting, electro-erosive cutting machine.<br />
2)� 40073 – Reuse Of C<strong>on</strong>diti<strong>on</strong>ally Released Radioactive Materials From NPP Decommissi<strong>on</strong>ing Applied In<br />
Motorway Bridges C<strong>on</strong>structi<strong>on</strong><br />
Michal Panik, Tomas Hrncir, Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)<br />
During the operati<strong>on</strong> and especially during decommissi<strong>on</strong>ing of nuclear installati<strong>on</strong> is produced c<strong>on</strong>siderable<br />
amount of solid materials (metals, n<strong>on</strong>-metals, building structures) that can fix radioactivity in forms of c<strong>on</strong>taminati<strong>on</strong> or<br />
activati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> materials present radioactive waste, part of radioactive waste may just slightly exceed limits for<br />
unc<strong>on</strong>diti<strong>on</strong>al release of materials into the envir<strong>on</strong>ment. On the other side, there is possible, after proving of defined<br />
safety limits fulfillment, to c<strong>on</strong>diti<strong>on</strong>ally release radioactive waste for special purpose. In opposite case it would be<br />
inevitable to dispose radioactive waste in radioactive waste repository. Approaches of different countries to release of<br />
materials vary and the extent of this issue processing is related to each approach. Requirements set down in Slovak<br />
Republic legislati<strong>on</strong> are given in the paper. Before the c<strong>on</strong>diti<strong>on</strong>al release of materials there must be d<strong>on</strong>e c<strong>on</strong>sistent<br />
analysis of the materials impact <strong>on</strong> the inhabitants and the envir<strong>on</strong>ment in short and l<strong>on</strong>g time period. <str<strong>on</strong>g>The</str<strong>on</strong>g> analysis<br />
comprises the evaluati<strong>on</strong> of c<strong>on</strong>sidered scenarios of specific utilizati<strong>on</strong> of c<strong>on</strong>diti<strong>on</strong>ally released materials. This analysis<br />
necessarily precedes the realizati<strong>on</strong> of utilizati<strong>on</strong>. Scenarios describing utilizati<strong>on</strong> of radioactive waste carb<strong>on</strong> steel in the<br />
motorway bridge building process is stated in the paper. Radioactive steel can be utilized in many parts of the bridge. In<br />
the paper it is described its use as reinforcement of piles. Short time period external irradiati<strong>on</strong> of workers and inhabitants<br />
is taken into account. Critical group (i.e. the group that gets the highest accumulated dose) of workers or inhabitants is<br />
chosen. Specific mass activity of released radioactive waste carb<strong>on</strong> steel is related to individual effective dose taken by<br />
critical group. Following legislati<strong>on</strong> rules, annual effective dose taken by critical group must not overstep the limit of 10<br />
μSv/year. <str<strong>on</strong>g>The</str<strong>on</strong>g> determinati<strong>on</strong> of value of the specific mass activity is the target of scenarios evaluating. Evaluati<strong>on</strong> of<br />
model scenarios can be realized with the appropriate calculati<strong>on</strong> tool. In the paper VISIPLAN 3D ALARA planning tool<br />
was<br />
Sessi<strong>on</strong><br />
chosen.<br />
L5 - H5 - H6<br />
3) 40071 – Modelling of Motorway Tunnels Scenario for Utilizati<strong>on</strong> of C<strong>on</strong>diti<strong>on</strong>ally Released Radioactive<br />
Materials<br />
Tomas Hrncir, Michal Panik, Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)<br />
C<strong>on</strong>siderable amount of solid radioactive waste is generated during the decommissi<strong>on</strong>ing of nuclear installati<strong>on</strong>s.<br />
Some of the materials can be released into the envir<strong>on</strong>ment either in a direct way, if they meet the releasing limits, or<br />
after the applicati<strong>on</strong> of some procedures leading to meeting the limits. If materials exceed these limits, they are treated,<br />
c<strong>on</strong>diti<strong>on</strong>ed and disposed of at appropriate repository of radioactive waste. Another possible releasing way is the<br />
c<strong>on</strong>diti<strong>on</strong>al release of materials, which is discussed in this paper. <str<strong>on</strong>g>The</str<strong>on</strong>g> basic principles of c<strong>on</strong>diti<strong>on</strong>al release as well as<br />
possibilities of reusing of the c<strong>on</strong>diti<strong>on</strong>ally released materials are described. One of these possibilities of the reusing was<br />
chosen and applicati<strong>on</strong> proposal of c<strong>on</strong>diti<strong>on</strong>al release of metal waste - steel reinforcement in the c<strong>on</strong>crete, which could<br />
be used for c<strong>on</strong>structi<strong>on</strong> of motorway tunnels, was created. <str<strong>on</strong>g>The</str<strong>on</strong>g> computer code Visiplan 4.0 3D ALARA planning tool<br />
software was used for the calculati<strong>on</strong> of effective individual dose for pers<strong>on</strong>nel c<strong>on</strong>structing the tunnel and for critical<br />
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Abstracts<br />
group related to scenario. Particular models for individual scenarios of c<strong>on</strong>diti<strong>on</strong>al release have been developed within<br />
the scope of this software code. <str<strong>on</strong>g>The</str<strong>on</strong>g> aim of the paper is to determine a level of the radioactivity of c<strong>on</strong>diti<strong>on</strong>al released<br />
materials to avoid over exceeding the value of annual individual effective dose 10microSv/year established by<br />
internati<strong>on</strong>al recommendati<strong>on</strong>s.<br />
4) 40117 – Estimate of Clearance Levels for Metal Materials C<strong>on</strong>taminated with Uranium<br />
Seiji Takeda, Hideo Kimura, JAEA (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Nuclear Safety Commissi<strong>on</strong> of Japan (NSC) published the draft report <strong>on</strong> the derivati<strong>on</strong> of clearance levels for<br />
the solid materials c<strong>on</strong>taminated with uranium (uranium-bearing wastes) in October 2009. <str<strong>on</strong>g>The</str<strong>on</strong>g> authors provide NSC with<br />
the estimated results of the clearance levels of major radi<strong>on</strong>uclides, U-234, U-235 and U-238, for metal reuse scenario.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> metal reuse scenario is categorized as two sub-scenarios <strong>on</strong> a series of recycling process of scrap metals and <strong>on</strong> reuse<br />
of items made from recycled metal and slag. By applying an effective dose criteri<strong>on</strong> of 10?Sv/y, the activity<br />
c<strong>on</strong>centrati<strong>on</strong>s are estimated from the deterministic dose calculati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> activity c<strong>on</strong>centrati<strong>on</strong>s for U-234, U-235 and<br />
U-238 are calculated to be 1.5Bq/g, 1.4Bq/g and 1.8Bq/g respectively. In order to c<strong>on</strong>firm the validity of the calculated<br />
c<strong>on</strong>centrati<strong>on</strong>s, we estimate the uncertainties <strong>on</strong> scenario descripti<strong>on</strong> after metal recycling and <strong>on</strong> parameter values used<br />
in the deterministic calculati<strong>on</strong>. It is difficult to rule out the possibility that a small amount of residue of slag generated<br />
from recycling process is disposed of as an industrial waste. Accordingly, the authors estimate the dose for a worker<br />
involved with landfill disposal of residue of slag and moreover the total uranium c<strong>on</strong>centrati<strong>on</strong> derived from the slag in<br />
the disposal site. <str<strong>on</strong>g>The</str<strong>on</strong>g> calculated dose of the worker for U-234, U-235 and U238 is about 0.05 times as low as that for the<br />
metal reuse scenario respectively. This result, therefore, leads to the predominance of estimating the dose <strong>on</strong> the basis of<br />
the metal reuse scenario. <str<strong>on</strong>g>The</str<strong>on</strong>g> total uranium c<strong>on</strong>centrati<strong>on</strong> derived from the slag in the disposal site is estimated to be<br />
lower than the mean value of measured uranium c<strong>on</strong>centrati<strong>on</strong> data in natural envir<strong>on</strong>ment of Japan. This result indicates<br />
that the landfill disposal of residue of slag hardly brings to increase uranium c<strong>on</strong>centrati<strong>on</strong> of natural origin. M<strong>on</strong>te<br />
Carlo-based uncertainty analysis was carried out in order to estimate the influence of parameter uncertainties to the result<br />
of deterministic calculati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> results of the uncertainty analysis, which are corresp<strong>on</strong>ding to the 97.5th percentile of<br />
minimum activity c<strong>on</strong>centrati<strong>on</strong> estimated by applying an effective dose criteri<strong>on</strong> of 100?Sv/y, are higher than those of<br />
deterministic calculati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> calculated activity c<strong>on</strong>centrati<strong>on</strong>s by deterministic calculati<strong>on</strong> for U-234, U235 and U-238<br />
were c<strong>on</strong>firmed from the results of both the analysis for an additi<strong>on</strong>al scenario <strong>on</strong> the landfill disposal of residue of slag<br />
and the M<strong>on</strong>te Carlo-based uncertainty analysis.<br />
SESSION H5: Panel "Advances in Knowledge Management for Radioactive Waste Disposal"<br />
Abstract Not Required<br />
SESSION H6: Coupled Process Modeling and Natural Analogues<br />
1) 40306 Keynote – A Discussi<strong>on</strong> of Key Issues in Coupled THM Processes in Clays, Rock Salt and Crystalline<br />
Rock with Bent<strong>on</strong>ite Buffer<br />
Chin-Fu Tsang, LBNL (USA)<br />
Abstract Not Available<br />
2) 40159 – Envir<strong>on</strong>mental Remediati<strong>on</strong> of High-Level Nuclear Waste in Geological Repository: modified<br />
Computer Code Creates Ultimate Benchmark in Natural systems<br />
Geoffrey Peter, Oreg<strong>on</strong> Institute of Technology Portland Center (USA)<br />
Isolati<strong>on</strong> of high-level nuclear waste in permanent geological repositories has been a major c<strong>on</strong>cern for over 30<br />
years due to the migrati<strong>on</strong> of dissolved radio nuclides reaching the water table (10,000-year compliance period) as water<br />
moves through the repository and the surrounding area. Repositories based <strong>on</strong> mathematical models allow for l<strong>on</strong>g-term<br />
geological phenomena and involve many approximati<strong>on</strong>s; however, experimental verificati<strong>on</strong> of l<strong>on</strong>g-term processes is<br />
impossible. Countries must determine if geological disposal is adequate for permanent storage. Many countries have<br />
extensively studied different aspects of safely c<strong>on</strong>fining the highly radioactive waste in an underground repository based<br />
<strong>on</strong> the unique geological compositi<strong>on</strong> at their selected repository locati<strong>on</strong>. This paper discusses two computer codes<br />
developed by various countries to study the coupled thermal, mechanical, and chemical process in these envir<strong>on</strong>ments,<br />
and the migrati<strong>on</strong> of radi<strong>on</strong>uclides. Further, this paper presents the results of a case study of the Magma-hydrothermal<br />
(MH) computer code, modified by the author, applied to nuclear waste repository analysis. <str<strong>on</strong>g>The</str<strong>on</strong>g> MH code verified by<br />
simulating natural systems thus, creating the ultimate benchmark. This approach based <strong>on</strong> processes similar to those<br />
expected near waste repositories currently occurring in natural systems. Keywords: High-Level Nuclear Waste,<br />
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Abstracts<br />
Repository, Envir<strong>on</strong>mental Remediati<strong>on</strong>, Computer Codes, Compliance Period, Benchmark.<br />
3) 40196 – Effect of the Residual Heat Release of the Nuclear Waste Stored in an Unsaturated Z<strong>on</strong>e <strong>on</strong><br />
Radi<strong>on</strong>uclide Release<br />
Lubna K. Hamdan, John C. Walt<strong>on</strong>, Arturo Woocay, University of Texas at El paso (USA)<br />
Over time, nuclear waste packages disposed in an unsaturated z<strong>on</strong>e geological repository, such as the proposed<br />
repository at Yucca Mountain, are expected to fail gradually due to localized and general corrosi<strong>on</strong>. As a result, water<br />
will have access to the nuclear waste and radi<strong>on</strong>uclides will be transported to the accessible envir<strong>on</strong>ment by ground water.<br />
In this paper we c<strong>on</strong>sider a serious failure case in which penetrati<strong>on</strong>s at the top and bottom of the waste package will<br />
allow water to flow through it (flow-through model). We introduce a new c<strong>on</strong>ceptual model that examines the effect of<br />
the residual heat release of the nuclear waste stored in an unsaturated envir<strong>on</strong>ment <strong>on</strong> radi<strong>on</strong>uclide release. This model<br />
predicts that the evaporati<strong>on</strong> of water at the hotter sheltered areas (from c<strong>on</strong>densate and seepage) inside the failed waste<br />
package will create a capillary pressure gradient that drives water to wick with its dissolved and suspended c<strong>on</strong>tents<br />
toward these relict areas, effectively preventing radi<strong>on</strong>uclides release. We drive a dimensi<strong>on</strong>less group to estimate the<br />
minimum length of the sheltered areas required to sequester radi<strong>on</strong>uclides and prevent their release. <str<strong>on</strong>g>The</str<strong>on</strong>g> implicati<strong>on</strong>s of<br />
this model <strong>on</strong> the performance of the proposed repository at Yucca Mountain or unsaturated z<strong>on</strong>e geological repositories<br />
in general are explored.<br />
4) 40072 – Evaluati<strong>on</strong> of behavior of rare earth elements based <strong>on</strong> determinati<strong>on</strong> of chemical state in<br />
groundwater in granite<br />
Yuhei Yamamoto, Daisuke Aosai, Takashi Mizuno, JAEA (Japan)<br />
Rare earth elements (REEs) in natural envir<strong>on</strong>ment have been studied as a useful geochemical tracer and analogues for trivalent<br />
actinides such as Am(III) which is c<strong>on</strong>tained in High-Level radioactive Waste (HLW). Since Am does not occur in natural<br />
envir<strong>on</strong>ment, behavior of REEs in deep groundwater gives us valuable informati<strong>on</strong> for research and development relating to the safety<br />
assessment of geological disposal of HLW. In groundwater, REEs often form complexes with aqueous and colloidal ligands according<br />
to their large i<strong>on</strong>ic potential (i<strong>on</strong>ic charge/i<strong>on</strong>ic radius). <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, behavior of REEs str<strong>on</strong>gly depends <strong>on</strong> physical and chemical<br />
properties of these complexes. However, it is difficult to speciate complexes of REEs in groundwater mainly due to difficulties in<br />
direct measurement of REEs complexes with their low c<strong>on</strong>centrati<strong>on</strong>s and alterati<strong>on</strong> of groundwater c<strong>on</strong>diti<strong>on</strong> during collecti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
aim of this study is determinati<strong>on</strong> of chemical states of REEs in groundwater by combinati<strong>on</strong> of ultrafiltrati<strong>on</strong> techniques maintaining<br />
in-situ pressure and anaerobic c<strong>on</strong>diti<strong>on</strong>s, speciati<strong>on</strong> calculati<strong>on</strong> taking care about c<strong>on</strong>tributi<strong>on</strong> of natural organic matters, and<br />
finger-printing method using REE pattern of stability c<strong>on</strong>stants for probable complexes of REEs in groundwater. Groundwater samples<br />
were collected from a borehole located in the 200 m substage of the Mizunami Underground Research Laboratory (MIU), Gifu, Japan.<br />
Our results suggest that colloidal ligands play an important roll <strong>on</strong> the behavior of REEs in groundwater.<br />
5) 40022 – Natural analogue studies of bent<strong>on</strong>ite reacti<strong>on</strong> under hyperalkaline c<strong>on</strong>diti<strong>on</strong>s: overview of <strong>on</strong>going<br />
work at the Zambales Ophiolite, Philippines<br />
Naoki Fujii, M. Yamakawa, RWMC (Japan); K. Namiki, Obayashi Corporati<strong>on</strong> (Japan);<br />
T. Sato, Hokkaido University (Japan); N. Shikaz<strong>on</strong>o, Keio University (Japan);<br />
C. A. Arcilla, C. Pascua, University of the Philippines (Philippines);<br />
W Russell Alexander, Bedrock Geosciences (Switzerland)<br />
Bent<strong>on</strong>ite is <strong>on</strong>e of the most safety-critical comp<strong>on</strong>ents of the engineered barrier system for the disposal c<strong>on</strong>cepts<br />
developed for many types of radioactive waste. However, bent<strong>on</strong>ite – especially the swelling clay comp<strong>on</strong>ent that<br />
c<strong>on</strong>tributes to its essential barrier functi<strong>on</strong>s – is unstable at high pH. To date, results from laboratory tests <strong>on</strong> bent<strong>on</strong>ite<br />
degradati<strong>on</strong> have been ambiguous as the reacti<strong>on</strong> rates are so slow as to be difficult to observe in the laboratory. As such,<br />
a key goal in this project is to examine the reacti<strong>on</strong> of natural bent<strong>on</strong>ites in c<strong>on</strong>tact with natural hyperalkaline<br />
groundwaters to determine if any l<strong>on</strong>g-term alterati<strong>on</strong> of the bent<strong>on</strong>ite occurs.<br />
Ophiolites have been identified as sources of hyperalkaline groundwaters that can be c<strong>on</strong>sidered natural analogues<br />
of the leachates produced by cementitious materials in repositories for radioactive waste. At the Zambales ophiolite in the<br />
Philippines, widespread active serpentinisati<strong>on</strong> results in hyperalkaline groundwaters with measured pH values of up to<br />
11.1, falling into the range typical of low-alkali cement porewaters. <str<strong>on</strong>g>The</str<strong>on</strong>g>se cements are presently being developed<br />
worldwide to minimise the geochemical perturbati<strong>on</strong>s which are expected to result from the use of OPC-based c<strong>on</strong>cretes<br />
(see Kamei et al., this c<strong>on</strong>ference, for details). In particular, it is hoped that the lower pH of the low-alkali cement<br />
leachates will reduce, or even avoid entirely, the potential degradati<strong>on</strong> of the bent<strong>on</strong>ite buffer which is expected at the<br />
higher pH levels (12.5 and above) comm<strong>on</strong> to OPC-based c<strong>on</strong>cretes. During recent field campaigns at two sites in the<br />
Zambales ophiolite (Mangatarem and Bigbiga), samples of bent<strong>on</strong>ite and the associated hyperalkaline groundwaters have<br />
been collected by drilling and trenching. At Mangatarem, qualitative data from a ‘fossil’ (i.e. no groundwater is currently<br />
present) reacti<strong>on</strong> z<strong>on</strong>e indicates some alterati<strong>on</strong> of the bent<strong>on</strong>ite to zeolite, serpentine and CSH phases. Preliminary<br />
reacti<strong>on</strong> path modelling suggests that the zeolites could have been produced as a product of smectite reacti<strong>on</strong> in the<br />
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Abstracts<br />
hyperalkaline groundwaters. Although not included in this calculati<strong>on</strong> to date, the CSH phases identified are completely<br />
c<strong>on</strong>sistent with reacti<strong>on</strong> of clays with hyperalkaline groundwaters, as seen at other sites worldwide.<br />
At the Bigbiga site, an active hyperalkaline groundwater/bent<strong>on</strong>ite reacti<strong>on</strong> z<strong>on</strong>e (at the base of the bent<strong>on</strong>ite<br />
deposit) has recently been drilled and samples are currently undergoing analysis. A comparis<strong>on</strong> of the data sets from both<br />
sites will be included in the presentati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper will also outline the potential future programme of research at these<br />
sites.<br />
6) 40063 – Natural Analogues of Cement: Overview of the Unique Systems in Jordan<br />
Gento Kamei, JAEA (Japan);<br />
W Russell Alexander, Bedrock Geosciences (Switzerland); Ian D. Clark, University of Ottawa (Canada);<br />
Paul Degnan, IAEA; Marcel Elie, Shell (UK); Hani Khoury, Elias Salameh, University of Jordan (Jordan);<br />
Ant<strong>on</strong>i E. Milodowski, British Geological Survey (UK); Alister F. Pitty, Pitty C<strong>on</strong>sulting (UK);<br />
John A.T. Smellie, C<strong>on</strong>terra (Sweden)<br />
In L/ILW repository designs, cement-based materials are expected to dominate – for example, the proposed Swiss<br />
repository will c<strong>on</strong>tain over 1.5 milli<strong>on</strong> t<strong>on</strong>nes of cementitious material. Models of cement evoluti<strong>on</strong> predict that leaching<br />
of the cement in the repository by groundwater will produce an initial stage of hyperalkaline (pH~13.5) leachates,<br />
dominated by alkali hydroxides, followed by a l<strong>on</strong>ger period of portlandite and CSH buffered (pH~12.5) leachates. It has<br />
also been predicted that the hyperalkaline porewater leached out of the near-field will interact with the repository host<br />
rock (and, where applicable, bent<strong>on</strong>ite buffer and backfill). This could possibly lead to deteriorati<strong>on</strong> of those features for<br />
which the host rock formati<strong>on</strong> and bent<strong>on</strong>ite were originally chosen.<br />
Here, the safety assessment implicati<strong>on</strong>s of the novel data from the Jordan Natural Analogue Study, which looked<br />
into interacti<strong>on</strong> of natural cementitious hyperalkaline leachates <strong>on</strong> repository host rocks and clays, are presented. Several<br />
sites across Jordan have been studied, but the focus here will be <strong>on</strong> two particularly c<strong>on</strong>trasting sites:<br />
• Maqarin in northern Jordan – this represents repository host rocks with advective groundwater systems.<br />
Hydrogeological, hydrochemical and structural data collected <strong>on</strong> the fractured rock at the site have been used to<br />
assess the likely implicati<strong>on</strong>s of hyperalkaine leachate interacti<strong>on</strong> <strong>on</strong> the l<strong>on</strong>g-term flow c<strong>on</strong>diti<strong>on</strong>s in similar<br />
repository host rocks (e.g. granites, fractured sediments) and this will be discussed in detail<br />
• Khushaym Matruk in south-central Jordan – this represents repository host rocks with diffusive groundwater<br />
systems. Here, hyperalkaline leachates have diffused through an impermeable, clay-rich sediment, so providing<br />
informati<strong>on</strong> <strong>on</strong> the likely c<strong>on</strong>trols <strong>on</strong> leachate interacti<strong>on</strong> in tight repository host rocks (e.g. clayst<strong>on</strong>es)<br />
In additi<strong>on</strong>, data are provided <strong>on</strong> the nature of the sec<strong>on</strong>dary phases produced following interacti<strong>on</strong> of the leachates<br />
with clays present at the sites. <str<strong>on</strong>g>The</str<strong>on</strong>g>se clays include mixed-layer illite/smectite and so are particularly good analogues of<br />
reacti<strong>on</strong> of cement leachates <strong>on</strong> the bent<strong>on</strong>ite buffer which is an integral part of the EBS in some L/ILW repository<br />
designs. This work will be c<strong>on</strong>trasted with that presented by Fujii et al (this c<strong>on</strong>ference) which is focussed <strong>on</strong> bent<strong>on</strong>ite<br />
reacti<strong>on</strong> in leachates from low alkali cements. <str<strong>on</strong>g>The</str<strong>on</strong>g>se cements are under c<strong>on</strong>siderati<strong>on</strong> for use in repositories where<br />
bent<strong>on</strong>ite and c<strong>on</strong>crete will be placed together as they produce lower pH leachates (pH 10 to 11) which are believed to be<br />
less aggressive to bent<strong>on</strong>ite than the higher pH leachates from OPC which are discussed here.<br />
SESSION D4: Panel "Applying Less<strong>on</strong>s Learned from Past D&D Activities"<br />
Abstract Not Required<br />
SESSION R2: Envir<strong>on</strong>mental Remediati<strong>on</strong><br />
1) 40261 – Reclamati<strong>on</strong> of Three In Situ Uranium Mines - Innovative Techniques<br />
Wallace Mays, W M Mining Company (USA)<br />
RECLAMATION OF THREE IN SITU URANIUM MINES IN TEXAS-INNOVATIVE APPROACHES By:<br />
Wallace Mays, President of IEC, Chairman and COO of Powertech Uranium, President W M Mining Company From<br />
1990 through 2010, Wallace Mays has been restoring the ground water and reclaiming the surface of three In Situ Leach<br />
Uranium Mines in south Texas; the Lamprecht, Zamzow and Pawnee In Situ Leach Mines located in Bee and Live Oak<br />
Counties in south Texas. <str<strong>on</strong>g>The</str<strong>on</strong>g>se mines were operated by Westinghouse Corporati<strong>on</strong> subsidiary Wyoming Minerals and by<br />
Interc<strong>on</strong>tinental Energy Corporati<strong>on</strong> (IEC). <str<strong>on</strong>g>The</str<strong>on</strong>g>se were am<strong>on</strong>g the first In Situ Mines operated and utilized high levels of<br />
amm<strong>on</strong>ia carb<strong>on</strong>ate, which complicated the ground water reclamati<strong>on</strong> project. IEC was acquired by Oren Bent<strong>on</strong>, who<br />
declared bankruptcy in 1995 in the middle of the ground water restorati<strong>on</strong> process. Westinghouse had set up an annuity<br />
to fund their reclamati<strong>on</strong> obligati<strong>on</strong>s. W. Mays formed a company, Cima Energy to c<strong>on</strong>tract to manage the reclamati<strong>on</strong><br />
and to finance the funding of the working capital to be reimbursed. <str<strong>on</strong>g>The</str<strong>on</strong>g>se ISL mines posed very difficult ground water<br />
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Abstracts<br />
restorati<strong>on</strong> and surface reclamati<strong>on</strong> problems as they were developed when the industry was developing the techniques<br />
that later were successful. In additi<strong>on</strong>, the reclamati<strong>on</strong> b<strong>on</strong>d was limited and required innovative techniques to restore and<br />
reclaim more efficiently. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper will describe the Restorati<strong>on</strong> Funding Methods and speak to issues related to<br />
determining b<strong>on</strong>ding and how these could be improved. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper will present a significantly enhanced ground water<br />
restorati<strong>on</strong> procedures, describing the theory and presenting the data from both Reverse Osmosis and Ground Water<br />
Sweep restorati<strong>on</strong> methods. Three complete ISL process facilities were dismantled, decommissi<strong>on</strong>ed and transported to<br />
licensed low level radioactive waste disposal. Innovative dec<strong>on</strong>taminati<strong>on</strong> procedures were developed and described in<br />
the paper. This paper describes the restorati<strong>on</strong> of pre mining ground water quality in three mines of more than 3.2<br />
kilometers of ground water by circulati<strong>on</strong> more than 3 billi<strong>on</strong> gall<strong>on</strong>s of ground water through reverse osmosis,<br />
dec<strong>on</strong>taminating, dismantling and disposal of three complete ISL Process Plants, removing, dec<strong>on</strong>taminating and<br />
disposing of more than 50 miles of 4 inch pvc pipe from the well fields, plugging and reclaiming more than 6,600 ISL<br />
wells, and transporting to licensed low level radioactive waste disposal sites more than 650 trucks of low level waste.<br />
Surface reclamati<strong>on</strong> procedures and problems will be presented.<br />
2) 40005 – Envir<strong>on</strong>mental remediati<strong>on</strong> Activities at the Ningyo-toge Uranium Mine, Japan<br />
Hiroshi Saito, Tomihiro Taki, JAEA (Japan)<br />
Ningyo-toge Uranium Mine is located at and around the boundary of Okayama and Tottori Prefectures, western part<br />
of Japan. In the Ningyo-toge Mine, explorati<strong>on</strong> activities had been carried out in 1950’s and 60’s after the outcrop was<br />
discovered in 1955. Mining activities using galleries and an open-pit had been carried out for sending uranium ores to the<br />
c<strong>on</strong>versi<strong>on</strong> and the enrichment plants to 1987 when the mining activities were terminated to begin the envir<strong>on</strong>mental<br />
remediati<strong>on</strong> activities.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>re are many facilities subject to the envir<strong>on</strong>mental remediati<strong>on</strong>, including a mill tailings p<strong>on</strong>d, a former open-pit<br />
mine and waste rock yards. <str<strong>on</strong>g>The</str<strong>on</strong>g> main purposes of the envir<strong>on</strong>mental remediati<strong>on</strong> comm<strong>on</strong> to these facilities, are to take<br />
measures to reduce the radiati<strong>on</strong> exposure from the exposure pathways to humans in future, and to prevent the occurrence<br />
of relevant envir<strong>on</strong>mental c<strong>on</strong>taminati<strong>on</strong>.<br />
So far, a great number of data have been acquired and technical methods have been examined for the future<br />
remediati<strong>on</strong>. And using the above-menti<strong>on</strong>ed data, JAEA has been c<strong>on</strong>ducting the remediati<strong>on</strong> activities at the related<br />
facilities. Am<strong>on</strong>g them, the mill tailings p<strong>on</strong>d, operated since 1965 with the approved volume about 40,000m3, has<br />
deposited mining waste and impounded mine water as a buffer reservoir before it is transferred to the water treatment<br />
facility. It is located at the upstream of the water-source river, and therefore, its presence is a cause for worry to the local<br />
residents. Also, social impact is thought to be extensive in case of an outflow incident of mill tailings, like dam failure by<br />
the earthquake. Thus the highest priority has been put to the p<strong>on</strong>d.<br />
JAEA has planned to c<strong>on</strong>duct the remediati<strong>on</strong> and close the p<strong>on</strong>d in coming couple of years. Some activities have<br />
already begun, and the results have been produced steadily. According to the current plan, the p<strong>on</strong>d will be covered by<br />
the multi-layered capping following dewatering and reshaping of mill tailings. <str<strong>on</strong>g>The</str<strong>on</strong>g> capping is composed of “rad<strong>on</strong><br />
barrier” for lowering rad<strong>on</strong>-gas dissipati<strong>on</strong> and dose rate, and “low-permeable protective layer” for protecting the rad<strong>on</strong><br />
barrier and reducing the amount of permeated rainwater. Natural material, including bent<strong>on</strong>ite and sand, is planned for<br />
use to alleviate the future maintenance. Currently, designing is underway for the upstream half of the p<strong>on</strong>d. Data will be<br />
accumulated after capping to verify its effectiveness, and if proved effective, it will be utilized for the capping of the<br />
downstream half of the p<strong>on</strong>d.<br />
3) 40092 – Rad<strong>on</strong> impact at a remediated uranium mine site in Japan<br />
Yuu Ishimori, JAEA (Japan)<br />
This paper mainly illustrates the rad<strong>on</strong> impact of the closed uranium mine site remediated in 2007. <str<strong>on</strong>g>The</str<strong>on</strong>g> site<br />
remediated is the waste rock site located <strong>on</strong> the steep slope of a hill about1.5 km upstream from a residential area al<strong>on</strong>g a<br />
main ravine. Major remedial acti<strong>on</strong> was to cover these waste rock yards with weathering granite soil. <str<strong>on</strong>g>The</str<strong>on</strong>g> rad<strong>on</strong> flux<br />
density after remediati<strong>on</strong> was intended to be 0.1 Bqm-2s-1 in c<strong>on</strong>siderati<strong>on</strong> with the natural background level around<br />
Ningyo-toge because there is no value of rad<strong>on</strong> flux density regulated in Japan. Our acti<strong>on</strong> decreased the rad<strong>on</strong><br />
c<strong>on</strong>centrati<strong>on</strong> in the site to natural background level, approximately from 10 to 40 Bqm-3, although relatively high<br />
c<strong>on</strong>centrati<strong>on</strong> in excess of 100 Bqm-3 was observed before remediati<strong>on</strong>. On the other hand, our acti<strong>on</strong> did not decrease<br />
the rad<strong>on</strong> c<strong>on</strong>centrati<strong>on</strong>s around the site in general. This fact proved that the limited source such as waste rocks affected<br />
the rad<strong>on</strong> c<strong>on</strong>centrati<strong>on</strong>s at neighboring area <strong>on</strong>ly. <str<strong>on</strong>g>The</str<strong>on</strong>g> similar tendencies were also observed in other envir<strong>on</strong>mental data<br />
such as rad<strong>on</strong> progeny c<strong>on</strong>centrati<strong>on</strong>s. In c<strong>on</strong>clusi<strong>on</strong>, these findings proved that our remedial acti<strong>on</strong> was successful<br />
against rad<strong>on</strong>. This fact will lead to more reas<strong>on</strong>able acti<strong>on</strong> plans for other closed mine sites.<br />
4) 40243 – Phosphate based remediati<strong>on</strong> techniques: interacti<strong>on</strong> of phosphate with uranium-bound calcite<br />
Chase Bovaird, Dawn Wellman, PNNL (USA)<br />
Despite several decades of studies, effective uranium cleanup strategies remain elusive for c<strong>on</strong>taminati<strong>on</strong> in deep<br />
subsurface settings that prevail in a number of Department of Energy sites in the western USA. Numerous strategies have<br />
been proposed, including ir<strong>on</strong> barriers, soluble reductive agents, and microbial stabilizati<strong>on</strong> via reducti<strong>on</strong> and<br />
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precipitati<strong>on</strong>, but have limited applicability for deep subsurface remediati<strong>on</strong> in an oxidative envir<strong>on</strong>ment. In-situ<br />
phosphate based remediati<strong>on</strong> techniques can potentially delay the precipitati<strong>on</strong> of phosphate phases for c<strong>on</strong>trolled in situ<br />
precipitati<strong>on</strong> of stabile phosphate phases to c<strong>on</strong>trol the l<strong>on</strong>g-term fate of uranium. <str<strong>on</strong>g>The</str<strong>on</strong>g> basic principles underlying<br />
phosphate stabilizati<strong>on</strong> is that aqueous phosphate (PO43-), whether injected as an aqueous soluti<strong>on</strong> or solubilized from a<br />
source reacts with heavy metals to form insoluble metal-phosphate minerals. <str<strong>on</strong>g>The</str<strong>on</strong>g> sorpti<strong>on</strong> of uranyl species <strong>on</strong>to minerals<br />
is dependent <strong>on</strong> the nature and availability of binding sites, soluti<strong>on</strong> compositi<strong>on</strong> and pH, and aqueous complexati<strong>on</strong>.<br />
Uranium can be sequestered either through i<strong>on</strong> exchange or surface complexati<strong>on</strong>, and the rates of release of uranium are<br />
dependent <strong>on</strong> the sorpti<strong>on</strong> mechanism. <str<strong>on</strong>g>The</str<strong>on</strong>g> Hanford Site in southeastern Washingt<strong>on</strong> State is a former nuclear defense<br />
producti<strong>on</strong> facility. Uranium has been identified as a c<strong>on</strong>taminant of c<strong>on</strong>cern for groundwater and the deep vadose z<strong>on</strong>e.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> vadose z<strong>on</strong>e is comprised of highly alkaline, calcareous sediment. EXAFS analyses at shallow depths suggest that<br />
uranium-rich calcite is <strong>on</strong>e of the major c<strong>on</strong>trolling phases. Calcite can also serve as a source of Ca2+ and CO32- i<strong>on</strong>s to<br />
form mobile, aqueous, uranyl-carb<strong>on</strong>ate species [Ca2UO2(CO3)3] under circumneutral to alkaline c<strong>on</strong>diti<strong>on</strong>s. Detailed<br />
understanding of the rate and mechanism of the interacti<strong>on</strong> between phosphate and uranium-rich calcite will allow a more<br />
effective design of aqueous phosphate-based infiltrati<strong>on</strong> strategies to minimize the mobilizati<strong>on</strong> of uranium during<br />
remediati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> objective of this investigati<strong>on</strong> was to evaluate the interacti<strong>on</strong> of phosphate species with uranium-rich<br />
calcite to determine the effects of geochemical c<strong>on</strong>diti<strong>on</strong>s <strong>on</strong> the partiti<strong>on</strong>ing of phosphate and its degradati<strong>on</strong> products<br />
with uranium-rich calcite, quantify the release of uranium from uranium-rich calcite based <strong>on</strong> the identity and<br />
c<strong>on</strong>centrati<strong>on</strong> of aqueous phosphate species, and quantify the rate and mechanism of uranium immobilizati<strong>on</strong> based <strong>on</strong><br />
the identity and c<strong>on</strong>centrati<strong>on</strong> of aqueous phosphate species. <str<strong>on</strong>g>The</str<strong>on</strong>g> informati<strong>on</strong> obtained from this line of inquiry is<br />
essential to effectively develop phosphate-based remediati<strong>on</strong> strategies for uranium in calcareous envir<strong>on</strong>ments.<br />
5) 40220 – Remediati<strong>on</strong> of Old Envir<strong>on</strong>mental Liabilities in <str<strong>on</strong>g>The</str<strong>on</strong>g> Nuclear Research Institute Rez plc<br />
Karel Svoboda, Josef Podlaha, Nuclear Research Institute Rez plc (Czech Republic)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Nuclear Research Institute Rez plc (NRI) after 55 years of activities in the nuclear field produced some<br />
envir<strong>on</strong>mental liabilities that shall be remedied. <str<strong>on</strong>g>The</str<strong>on</strong>g>re are three areas of remediati<strong>on</strong>: (1) decommissi<strong>on</strong>ing of old<br />
obsolete facilities (e.g. decay tanks, RAW treatment technology, special sewage system), (2) processing of RAW from<br />
operati<strong>on</strong> and dismantling of nuclear facilities, and (3) eliminati<strong>on</strong> of spent fuel from research nuclear reactors operated<br />
by the NRI. <str<strong>on</strong>g>The</str<strong>on</strong>g> goal is to remedy the envir<strong>on</strong>mental liabilities and eliminate the potential negative impact <strong>on</strong> the<br />
envir<strong>on</strong>ment. Remediati<strong>on</strong> of the envir<strong>on</strong>mental liabilities started in 2003 and will be finished in 2014. <str<strong>on</strong>g>The</str<strong>on</strong>g> character of<br />
the envir<strong>on</strong>mental liabilities is very specific and requires special remediati<strong>on</strong> procedures. Special technologies are being<br />
developed with assistance of external subc<strong>on</strong>tractors. <str<strong>on</strong>g>The</str<strong>on</strong>g> NRI has gained many experiences in the field of RAW<br />
management and decommissi<strong>on</strong>ing of nuclear facilities and will use its facilities, experienced staff and all relevant data<br />
needed for the successful realizati<strong>on</strong> of the remediati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> most significant items of envir<strong>on</strong>mental liabilities are<br />
described in the paper together with informati<strong>on</strong> about the history, the current state, the progress, and the future activities<br />
in the field of remediati<strong>on</strong> of envir<strong>on</strong>mental liabilities in the NRI.<br />
SESSION G2: IAEA Topical for Disused Sealed Radioactive Sources (DSRS)<br />
1) 40028 – <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> initiatives addressing the safety and security of Disused Sealed Radioactive Sources<br />
(DSRS)<br />
Robin Heard, IAEA<br />
High activity radioactive sources provide great benefit to humanity through their utilizati<strong>on</strong> in agriculture, industry,<br />
medicine, research and educati<strong>on</strong>, and the vast majority is used in well-c<strong>on</strong>trolled envir<strong>on</strong>ments. N<strong>on</strong>e-the-less, c<strong>on</strong>trol<br />
has been lost over a small fracti<strong>on</strong> of those sources resulting in accidents of which some had serious – even fatal –<br />
c<strong>on</strong>sequences. Indeed, accidents and incidents involving radioactive sources indicate that the existing regime for the<br />
c<strong>on</strong>trol of sources needs improvement. Additi<strong>on</strong>ally, today’s global security envir<strong>on</strong>ment requires more determined<br />
efforts to properly c<strong>on</strong>trol radioactive sources. C<strong>on</strong>sequently, the current regimes must be strengthened in order to ensure<br />
c<strong>on</strong>trol over sources that are outside of regulatory c<strong>on</strong>trol (orphan sources), as well as for sources that are vulnerable to<br />
loss, misuse, theft, or malicious use. Besides improving the existing situati<strong>on</strong>, appropriate norms and standards at the<br />
nati<strong>on</strong>al and internati<strong>on</strong>al levels must c<strong>on</strong>tinue to be developed to ensure the l<strong>on</strong>g-term sustainability of c<strong>on</strong>trol over<br />
radioactive sources. In order to improve the existing situati<strong>on</strong>, c<strong>on</strong>certed nati<strong>on</strong>al and internati<strong>on</strong>al efforts are needed and,<br />
to some degree, are being implemented to strengthen the safety and security of sources in use, as well as to improve the<br />
c<strong>on</strong>trol of disused sources located at numerous facilities throughout the world. More efforts must also be made to identify,<br />
recover, and bring into c<strong>on</strong>trol orphan sources. <str<strong>on</strong>g>The</str<strong>on</strong>g> IAEA works closely with Member States to improve the safety and<br />
security of radioactive sources worldwide. Besides the IAEA Technical Assistance Programme and Technical<br />
Cooperati<strong>on</strong> Fund, d<strong>on</strong>or States provide significant financial c<strong>on</strong>tributi<strong>on</strong>s to the Nuclear Security Fund and/or direct<br />
technical support to other States to recover, c<strong>on</strong>diti<strong>on</strong> and transfer disused sources into safe and secure storage facilities<br />
and to upgrade the physical protecti<strong>on</strong> of sources that are in use. Under the USA-Russian Federati<strong>on</strong>-IAEA (“Tripartite”)<br />
Initiative, for example, disused sources of a total activity of 2120 TBq (57251 Ci) were recovered and transported into<br />
safe and secure storage facilities in six countries of the former Soviet Uni<strong>on</strong>. Additi<strong>on</strong>ally, physical protecti<strong>on</strong> upgrades<br />
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Abstracts<br />
were performed in thirteen former Soviet Uni<strong>on</strong> republics at facilities using or storing high activity radioactive sources.<br />
Canada has also provided funding for projects related to the safety and security of radioactive sources in the same regi<strong>on</strong>.<br />
Additi<strong>on</strong>ally, the EU and other countries are making regular and significant c<strong>on</strong>tributi<strong>on</strong>s to the IAEA for projects aimed<br />
at upgrading the safety and security of radioactive sources in South-Eastern Europe, the Middle East, Asia and Africa.<br />
Depending <strong>on</strong> the status of the radioactive source (in use, disused, or orphan) and the actual technical, safety and security<br />
situati<strong>on</strong>, several opti<strong>on</strong>s exist to ensure the source is properly brought or maintained under c<strong>on</strong>trol. This paper will<br />
describe those opti<strong>on</strong>s and the systematic approach followed by the IAEA in deciding <strong>on</strong> the most appropriate acti<strong>on</strong>s to<br />
take for the high activity sources that need to be recovered or removed from the countries under that request assistance.<br />
2) 40303 – Current situati<strong>on</strong> and Management Plan of Radioactive Sources in Japan<br />
Hirokuni Ito, Tadashi Ishii, Tomokazu Ueta, Takao Nakaya, Kenya Suyama, MEXT (Japan)<br />
1, Status of Radioactive Material Distributi<strong>on</strong> in Japan Almost all radioactive products in Japan are directly<br />
imported or produced by using imported radioactive materials. Approximately 99% (in terms of radioactivity; as of 2009)<br />
of sealed radioactive sources distributed in Japan are imported and supplied through Japan Radio Isotope Associati<strong>on</strong><br />
(JRIA).<br />
2, Disused Sealed Radioactive Sources (DSRS) and Orphan sources Substantially, in Japan the users of the sealed<br />
radioactive sources will return to manufacturers or distributors. JRIA collects the DSRS based <strong>on</strong> the sales c<strong>on</strong>tract<br />
between JRIA and the purchasers of the sealed radioactive sources. <str<strong>on</strong>g>The</str<strong>on</strong>g> collected DSRS are tested in JRIA’s facility to<br />
check the surface c<strong>on</strong>taminati<strong>on</strong> and the radioactivity for the transport safety. JRIA also receives orphan radioactive<br />
sources in Japan in accordance with MEXT’s administrative instructi<strong>on</strong> if they are found.<br />
JRIA returns collected DSRS, except for the products using very short half life nuclides, to the radioactive source<br />
manufacturers in accordance with internati<strong>on</strong>al guidelines and the import agreement between JRIA and the source<br />
manufacturers.<br />
JRIA keeps the collected DSRS in their own storage facility in cases where they can not return them to the<br />
radioactive source manufacturers. However, generally speaking, such DSRS kept temporary in the storage facility of<br />
JRIA have been returned successively to the manufacturer, through the discussi<strong>on</strong> am<strong>on</strong>g relevant parties if necessary. In<br />
Japan, by the system that JRIA receives disused sealed sources based <strong>on</strong> the sales c<strong>on</strong>tract menti<strong>on</strong>ed above, orphan<br />
sources are scarcely found. Nevertheless, in such case, they will be picked up and kept safely in storage facility of JRIA.<br />
3, L<strong>on</strong>g term Management Plan of DSRS in Japan <str<strong>on</strong>g>The</str<strong>on</strong>g>re is no disposal facility for DSRS in Japan. But as we<br />
explained above, it is not the serious issue which should be resolved so<strong>on</strong>. This is because i) almost all of DSRS are<br />
returned to source manufacturers, ii) JRIA has still enough storage capacity, iii) and the number of DSRS stored in JRIA<br />
is settled.<br />
We understand the potential necessity of the disposal facility of DSRS depending <strong>on</strong> the number of stored DSRS.<br />
But c<strong>on</strong>sidering current situati<strong>on</strong>, it is not required to c<strong>on</strong>struct the additi<strong>on</strong>al storage facility or the disposal facility for<br />
DSRS in Japan. Of course, this view depends <strong>on</strong> the increase rate of stored DSRS and the capacity of the storage facility<br />
in future. We would cooperate with the internati<strong>on</strong>al society and keep attenti<strong>on</strong> to the status of DSRS in Japan for the<br />
safety regulati<strong>on</strong> of the radioactive source c<strong>on</strong>sidering security aspects.<br />
3) 40060 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Deployment of the Mobile Hot Cell to C<strong>on</strong>diti<strong>on</strong> High Activity Disused Sealed Radioactive<br />
Sources (DSRS) for L<strong>on</strong>g Term Storage or Removal<br />
Gerhardus R. Liebenberg, South African Nuclear Energy Corporati<strong>on</strong> (Necsa) (South Africa)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy Agency (IAEA) Waste Technology Secti<strong>on</strong> with additi<strong>on</strong>al support from the U.S.<br />
Nati<strong>on</strong>al Nuclear Security Agency (NNSA) through the IAEA Nuclear Security Fund has funded the design, fabricati<strong>on</strong>,<br />
evaluati<strong>on</strong>, and testing of a mobile hot cell intended to address the problem of high activity disused sealed radioactive<br />
sources (DSRS) in obsolete irradiati<strong>on</strong> devices such as teletherapy heads and dry irradiators.<br />
Operati<strong>on</strong>s to c<strong>on</strong>diti<strong>on</strong> high activity DSRS using the mobile hot cell has successfully been undertaken in various<br />
countries since April 2009. <str<strong>on</strong>g>The</str<strong>on</strong>g> project was initially targeting the African c<strong>on</strong>tinent but is now also expanding to other<br />
parts of the world such as Latin America and Asia. <str<strong>on</strong>g>The</str<strong>on</strong>g> mobile hot cell allows for source removal, characterizati<strong>on</strong>,<br />
c<strong>on</strong>solidati<strong>on</strong>, repackaging in stainless steel capsules as special form, and secure storage of high risk DSRS in modern<br />
l<strong>on</strong>g term storage shields at single sites in each IAEA Member State.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> mobile hot cell and related equipment is transported in two shipping c<strong>on</strong>tainers to a specific country where the<br />
following process takes place: - Assembly of hot cell - Removal of high activity DSRS from working shields,<br />
encapsulati<strong>on</strong> into a stainless steel capsule to obtain special form status and placement into a l<strong>on</strong>g term storage shield -<br />
C<strong>on</strong>diti<strong>on</strong>ing of any other spent sources the country may require. - Dismantling of the hot cell - Shipping equipment out<br />
of country.<br />
This presentati<strong>on</strong> will discuss the design of the mobile hot cell as well as the deployment of the unit for<br />
manipulati<strong>on</strong> of high activity DSRS in various countries worldwide. As a result of this project, excess high activity<br />
DSRS could be managed safely and securely and possibly be more easily repatriated to their country of origin for<br />
appropriate final dispositi<strong>on</strong>.<br />
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4) 40266 – Problems with Packaged Sources in Foreign Countries<br />
James Matzke, John Zarling, Cristy Abeyta, Joseph A. Tompkins, LANL (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Global Threat Reducti<strong>on</strong> Initiative’s (GTRI) Off-Site Source Recovery Project (OSRP), which is administered<br />
by the Los Alamos Nati<strong>on</strong>al Laboratory (LANL), removes excess, unwanted, aband<strong>on</strong>ed, or orphan radioactive sealed<br />
sources that pose a potential risk to health, safety, and nati<strong>on</strong>al security. In total, GTRI/OSRP has been able to recover<br />
more than 19,000 excess and unwanted sealed sources from over 750 sites. In additi<strong>on</strong> to transuranic sources, the<br />
GTRI/OSRP missi<strong>on</strong> now includes recovery of beta/gamma emitting sources, which are of c<strong>on</strong>cern to both the U.S.<br />
government and the <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy Agency (IAEA). This paper provides a synopsis of cooperative efforts<br />
in foreign countries to remove sealed sources by discussing three topical areas: 1) <str<strong>on</strong>g>The</str<strong>on</strong>g> Regi<strong>on</strong>al Partnership with the<br />
<str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy Agency; 2) Challenges in repatriating sealed sources; and 3) Opti<strong>on</strong>s for repatriating sealed<br />
sources.<br />
5) 40085 – <str<strong>on</strong>g>The</str<strong>on</strong>g> IAEA's approach to the security of radioactive material<br />
Robin Heard, IAEA<br />
Over the past decade, the threat has increased of terrorism and other malevolent acts by terrorist groups and other<br />
malicious n<strong>on</strong>-State actors, involving the potential use of radioactive materials. This has led to an internati<strong>on</strong>al effort to<br />
build a nuclear security framework and regime, both for preventi<strong>on</strong> and c<strong>on</strong>sequence management. Legally binding and<br />
n<strong>on</strong>-binding internati<strong>on</strong>al instruments have been established that form the internati<strong>on</strong>al framework for an effective<br />
nuclear security regime. Adherence to and implementati<strong>on</strong> of these instruments is vital for effective nuclear security.<br />
IAEA implements a comprehensive programme to assist States in strengthening their nuclear security. <str<strong>on</strong>g>The</str<strong>on</strong>g> third Nuclear<br />
Security Plan covers the period 2010–2013. Through the implementati<strong>on</strong> of these plans, IAEA c<strong>on</strong>ducts advisory<br />
services and provides technical advice, support and training. It also addresses the l<strong>on</strong>ger-term effort of development of<br />
nuclear security guidance and it facilitates outreach and informati<strong>on</strong> exchange through databases, c<strong>on</strong>ferences,<br />
workshops and fellowships. Nuclear security issues relating to the preventi<strong>on</strong> and detecti<strong>on</strong> of, and resp<strong>on</strong>se to, theft,<br />
sabotage, unauthorized access and illegal transfer or other malicious acts involving nuclear material and other radioactive<br />
substances and their associated facilities are addressed in the IAEA Nuclear Security Series of publicati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g>se<br />
publicati<strong>on</strong>s are c<strong>on</strong>sistent with, and complement, internati<strong>on</strong>al nuclear security instruments, such as the Code of<br />
C<strong>on</strong>duct <strong>on</strong> the Safety and Security of Radioactive Sources. Nuclear security missi<strong>on</strong>s, evaluati<strong>on</strong>s and technical visits<br />
c<strong>on</strong>tinue to be the Agency’s main tool for helping States to assess their nuclear security needs, and provide a basis for<br />
formulating plans of acti<strong>on</strong> for improving nuclear security. <str<strong>on</strong>g>The</str<strong>on</strong>g> needs identified by such missi<strong>on</strong>s can be subsequently<br />
addressed by the State al<strong>on</strong>e, in c<strong>on</strong>juncti<strong>on</strong> with Agency support, or with the assistance of a bilateral partner. Annually,<br />
the IAEA c<strong>on</strong>ducts more than 60 training events for Member States as well as for N<strong>on</strong>-Member States. <str<strong>on</strong>g>The</str<strong>on</strong>g>se are based<br />
<strong>on</strong> findings and insights resulting from the various advisory missi<strong>on</strong>s and organized in resp<strong>on</strong>se to the requests<br />
formulated by the States themselves. Providing urgently needed technical upgrades and equipment has been a foundati<strong>on</strong><br />
for IAEA assistance to States in enhancing the security of radioactive material since the establishment of the Nuclear<br />
Security Programme. <str<strong>on</strong>g>The</str<strong>on</strong>g> equipment needed was provided to States as follow-up to assessment missi<strong>on</strong>s and the training<br />
needed to operate the equipment was arranged in separate events.<br />
6) 40058 – Radioactive Waste Management in Leban<strong>on</strong><br />
Munzna Assi, Lebanese Atomic Energy Commissi<strong>on</strong> (Leban<strong>on</strong>)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> disused sealed radioactive sources including orphan sources in Leban<strong>on</strong>, al<strong>on</strong>g with the growing industry of<br />
sealed radioactive sources in medical, industrial and research fields have posed a serious problem for authorities as well<br />
as users due to the lack of a nati<strong>on</strong>al store for disused radioactive sources. Assistance form <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy<br />
Agency (IAEA) was requested to c<strong>on</strong>diti<strong>on</strong> and store disused radium needles and tubes present at two facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
missi<strong>on</strong> took place <strong>on</strong> July 25, 2001 and was organized by the (IAEA) in cooperati<strong>on</strong> with the Lebanese Atomic Energy<br />
Commissi<strong>on</strong> (LAEC). Other disused radioactive sources were kept in the facilities till a safer and securer soluti<strong>on</strong> is<br />
provided; however orphan sources, found mainly during export c<strong>on</strong>trol, were brought and stored temporarily in LAEC.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> necessity of a safe and secure store became a must. Prior to October 2005, there was no clear legal basis for<br />
establishing such store for disused radioactive sources, until the ministerial decree no 15512 dated October 19, 2005<br />
(related to the implementati<strong>on</strong> of decree-law no 105/83) was issued which clearly stated that “<str<strong>on</strong>g>The</str<strong>on</strong>g> LAEC (Lebanese<br />
Atomic Energy Commissi<strong>on</strong>) shall, in cooperati<strong>on</strong> with the Ministry of Public Health, establish a practical mechanism<br />
for safe disposal of radioactive waste”. Following this, the work <strong>on</strong> inventory of disused sealed sources al<strong>on</strong>g with<br />
collecting orphan sources and placing them temporarily in LAEC was legally supported. Moreover, several missi<strong>on</strong>s<br />
were planned to repatriate category I and II sources, <strong>on</strong>e of which was completed specifically in August 2009; other<br />
missi<strong>on</strong>s are being worked <strong>on</strong>. In 2008, a nati<strong>on</strong>al technical cooperati<strong>on</strong> project with the <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Atomic Energy<br />
Agency, IAEA, was launched. Under the reference TC number LEB3002, the project was entitled “"Assistance in the<br />
establishment of a safe temporary nati<strong>on</strong>al storage at the Lebanese Atomic Energy Commissi<strong>on</strong> for orphan sources and<br />
radioactive waste" which cycle is 2009-2011. Under this project, a nati<strong>on</strong>al store for radioactive sources in the third<br />
basement of LAEC is being established. <str<strong>on</strong>g>The</str<strong>on</strong>g> area is being rec<strong>on</strong>structed currently and will be equipped when ready under<br />
LEB3002 project. Al<strong>on</strong>g with this, a system for sealed disused sources management has been prepared, part of which is<br />
applied now and the rest will be applied up<strong>on</strong> the establishment of the store. This paper will cover the inventory<br />
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Abstracts<br />
collecti<strong>on</strong> process, the study for the establishment of this store, the present and prospective waste management system,<br />
and the the waste acceptance criteria.<br />
7) 40029 – <str<strong>on</strong>g>The</str<strong>on</strong>g> ultimate soluti<strong>on</strong> – disposal of Disused Sealed Radioactive Sources (DSRS)<br />
Robin Heard, IAEA<br />
For countries with no access to existing or planned geological disposal facilities for radioactive wastes, the <strong>on</strong>ly<br />
opti<strong>on</strong>s for managing high activity or l<strong>on</strong>g-lived disused radioactive sources are to store them indefinitely, return them to<br />
the supplier or find an alternative method of disposal. Disused sealed radioactive sources (DSRS) pose an unacceptable<br />
radiological and security risk if not properly managed. Out of c<strong>on</strong>trol sources have already led to many high-profile<br />
incidents or accidents. Countries without soluti<strong>on</strong>s in place need to c<strong>on</strong>sider the future management of DSRSs urgently.<br />
In the frame of a regi<strong>on</strong>al Technical Cooperati<strong>on</strong> (TC) project, a number of countries in the African regi<strong>on</strong> have come<br />
together under the auspices of the IAEA to explore the opti<strong>on</strong> of a Borehole Disposal C<strong>on</strong>cept (BDC) for their small<br />
inventories of DSRSs.<br />
Disposal in boreholes is intended to be simple and effective, meeting the same high standards of l<strong>on</strong>g-term<br />
radiological safety as any other type of radioactive waste disposal. It is believed that the BDC can be readily deployed<br />
with simple, cost-effective technologies. <str<strong>on</strong>g>The</str<strong>on</strong>g>se are appropriate both to the relatively small amounts and activities of the<br />
wastes and the resources that can realistically be found in African countries. <str<strong>on</strong>g>The</str<strong>on</strong>g> South African Nuclear Energy<br />
Corporati<strong>on</strong> Ltd (Necsa) has carried out project development and dem<strong>on</strong>strati<strong>on</strong> activities since 1996. <str<strong>on</strong>g>The</str<strong>on</strong>g> project looked<br />
into the technical feasibility, safety and ec<strong>on</strong>omic viability of BDC under the social, ec<strong>on</strong>omic, envir<strong>on</strong>mental and<br />
infrastructural c<strong>on</strong>diti<strong>on</strong>s currently prevalent in Africa. C<strong>on</strong>ceptually, the disposal c<strong>on</strong>cept comprises a borehole<br />
(diameter ranging from 150 to 260 mm) drilled down to a depth ranging from 30 to 100 metres. <str<strong>on</strong>g>The</str<strong>on</strong>g> depth will be<br />
dependent <strong>on</strong> the site-specific safety assessment. <str<strong>on</strong>g>The</str<strong>on</strong>g> borehole will have a casing with a plug at the bottom. Grouting will<br />
then be applied to seal the annulus and all fractures and crevices outside of the casing. <str<strong>on</strong>g>The</str<strong>on</strong>g> spacing of waste packages is<br />
~1 metre. <str<strong>on</strong>g>The</str<strong>on</strong>g> space between packages is backfilled with a suitable material such as cement or c<strong>on</strong>crete grout. In the<br />
generic design of the Borehole Disposal C<strong>on</strong>cept, a 100-meter deep borehole is to be filled with 50 packages up to the<br />
depth of 50 metres. <str<strong>on</strong>g>The</str<strong>on</strong>g> rest will be backfilled with c<strong>on</strong>crete to act as a borehole plug.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> project was completed in 2004 and subject to an IAEA peer review by an independent group of internati<strong>on</strong>al<br />
experts in April 2005. One of the main outcomes of the internati<strong>on</strong>al peer review was the positive statement by the expert<br />
team that the BDC developed by Necsa had been dem<strong>on</strong>strated to be a safe, ec<strong>on</strong>omic, practical and permanent means of<br />
disposing of disused radioactive sealed sources.<br />
Implementati<strong>on</strong> is near at hand with work being d<strong>on</strong>e in Ghana with support from the IAEA. Here the site selecti<strong>on</strong><br />
is complete and studies are being carried out to test the site parameters for inclusi<strong>on</strong> into the safety assessment.<br />
SESSION L6: Waste Treatment<br />
1) 40055 – Drying System For Radioactivated Metal Waste From Nuclear Power Stati<strong>on</strong><br />
Nobuhito Ogaki, Yasushi Ooishi, Hir<strong>on</strong>ori Takabayashi, Masamichi Obata, Taichi Horimoto,<br />
Toshiba Corporati<strong>on</strong> (Japan)<br />
High dose rate metal waste from core internals, BWR channel box or c<strong>on</strong>trol rod is stored in fuel pool or site bunker<br />
pool. Waste form for final disposal of these high dose rate metal waste should elinimate water to prevent hydrogen gas<br />
which is caused by radialysis of water. Toshiba's newly developed drying system enables short drying time and easy<br />
maintenance. Toshiba will provide the total system to fabricate the waste form for high dose rate metal waste.<br />
2) 40186 – Macroporous Catalysts for Hydrothermal Oxidati<strong>on</strong> of Metallorganic Complexes at Liquid<br />
Radioactive Waste Treatment<br />
Valentin Avramenko, Dmitry Marinin, Vitaly Mayorov, Alexander Mir<strong>on</strong>enko, Marina Palamarchuk,<br />
Valentin Sergienko, Institute of Chemistry FEDRAS (Russia)<br />
One of the main problems of liquid radioactive waste (LRW) management is c<strong>on</strong>cerned with treatment of<br />
dec<strong>on</strong>taminati<strong>on</strong> waters c<strong>on</strong>taining organic ligands. <str<strong>on</strong>g>The</str<strong>on</strong>g> organic ligands like oxalic, citric and ethylenediaminetetraacetic<br />
acids form stable complexes with radi<strong>on</strong>uclides which puts restricti<strong>on</strong>s <strong>on</strong> applicati<strong>on</strong> of many technologies of LRW<br />
management. One of the ways of destructi<strong>on</strong> of metallorganic complexes c<strong>on</strong>sists in using the catalytic oxidati<strong>on</strong>.<br />
However, the heterophase catalytic oxidati<strong>on</strong> is rather problematic due to formati<strong>on</strong> of metal oxides <strong>on</strong> the catalyst<br />
surface and calmatati<strong>on</strong> of meso- and micropores. A possible soluti<strong>on</strong> of the above problem can be found in synthesis of<br />
macroporous catalysts for oxidati<strong>on</strong> having a regular macroporous structure. <str<strong>on</strong>g>The</str<strong>on</strong>g> present paper describes the template<br />
synthesis of macroporous metalloxide catalysts performed with using siloxane-acrylate microemulsi<strong>on</strong>s as templates. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
method for impregnati<strong>on</strong> of precious metals (PM) particles into the template, which enables <strong>on</strong>e to produce PM<br />
nanoparticles of a specific size and immobilize them in the porous structure of the synthesized metalloxide catalysts, is<br />
76
Abstracts<br />
presented. A possible mechanism of the synthesis of macroporous catalysts is suggested and the comparis<strong>on</strong> of the<br />
electr<strong>on</strong>ic and phot<strong>on</strong>-correlati<strong>on</strong> spectroscopy results obtained at different stages of catalysts synthesis was c<strong>on</strong>ducted.<br />
3) 40157 – Carb<strong>on</strong>aceous radioactive waste treatment<br />
Gerard Laurent, EDF/CIDEN (France)<br />
In the carb<strong>on</strong>aceous waste, the aim is to isolate and c<strong>on</strong>fine for storage purposes the volatile radi<strong>on</strong>uclides such as<br />
tritium (3H), chlorine-36 (36Cl) and, notably, carb<strong>on</strong> isotopes, in particular radioactive isotope 14C (referred to hereafter<br />
as "carb<strong>on</strong>-14").<br />
For this purpose, the inventi<strong>on</strong> includes two types of treatment of this carb<strong>on</strong>aceous waste: - a first type of treatment<br />
to obtain a carb<strong>on</strong> oxide, such as carb<strong>on</strong> m<strong>on</strong>oxide and/or carb<strong>on</strong> dioxide, the carb<strong>on</strong> element of which is the isotope<br />
carb<strong>on</strong>-14, and - a sec<strong>on</strong>d type of treatment of this carb<strong>on</strong> oxide to obtain a solid precipitate by reacti<strong>on</strong> with a chosen<br />
element such as, for example, calcium.<br />
This sec<strong>on</strong>d type of treatment, referred to as "carb<strong>on</strong>ati<strong>on</strong>", c<strong>on</strong>sists, for example, in bubbling the carb<strong>on</strong> oxide<br />
through a soluti<strong>on</strong> c<strong>on</strong>taining quick lime (when the chosen element is calcium). <str<strong>on</strong>g>The</str<strong>on</strong>g> solid precipitate obtained (typically<br />
CaCO3 calcite, the carb<strong>on</strong> element of which is the isotope 14C) may then be c<strong>on</strong>fined for l<strong>on</strong>g-term storage in bulk in<br />
c<strong>on</strong>tainers stored above-ground or buried under a layer of earth of a certain thickness, beneath a hill, for example. A<br />
variant shall be noted here, c<strong>on</strong>sisting in making the carb<strong>on</strong> oxide react with an element other than calcium, such as<br />
magnesium (or other metals), to obtain magnesite MgCO3. Essentially, this sec<strong>on</strong>d type of treatment generally aims to<br />
obtain an insoluble solid precipitate, made up of carb<strong>on</strong>ates and/or salts comprising the carb<strong>on</strong> element.<br />
4) 40163 – Impermeable graphite: A new development for the waste management of irradiated graphite<br />
Johannes Fachinger, Karl-Heinz Grosse, Furnances Nuclear Applicati<strong>on</strong>s Grenoble (Germany);<br />
Richard Seemann, Milan Hrovat ALD (Germany)<br />
Graphite is a geological stable material proven by its natural occurrence. However its porous structure anticipates<br />
the use of graphite as l<strong>on</strong>g term stable waste matrix for final disposal. A slow corrosi<strong>on</strong> in aquatic phases can be induced<br />
by high irradiati<strong>on</strong> doses in the range of 10E-5 to 10E-7 g/m²d. <str<strong>on</strong>g>The</str<strong>on</strong>g> porous structure is related to large surface areas and<br />
therefore the radiati<strong>on</strong> induced corrosi<strong>on</strong>s process cannot be neglected for final disposal. Furthermore aqueous phases<br />
will penetrate into the pore system and radi<strong>on</strong>uclides adsorbed <strong>on</strong> the surface will be dissolved. All this problems can be<br />
solved with a graphite material with a closed pore system. A graphite composite material with an inorganic binder has<br />
been developed with a density > 99,9 % of theoretical density and therefore a negligible porosity. A first draft calculati<strong>on</strong><br />
predicts that the life time of such a material will be at least 2 orders of magnitude higher than porous graphite. This<br />
material represents a l<strong>on</strong>g term stable leaching resistant matrix for the embedding of i-graphite. Granulated i-graphite will<br />
be mixed with natural graphite and inorganic binder and pressed as block. Other radioactive wastes can be embedded in<br />
this matrix additi<strong>on</strong>ally, e.g. coated particles of spent fuel from HTR reactors. First investigati<strong>on</strong>s proofed the expected<br />
pore free structure and good mechanical strength properties. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper further will present a selecti<strong>on</strong> of potential<br />
addit<strong>on</strong>al applicati<strong>on</strong>s of the new material as embedding material for of different nuclear waste streams like noble metals<br />
from reprocessing or iodine.<br />
5) 40165 – THOR® Steam Reforming Technology for the Treatment of I<strong>on</strong> Exchange Resins and More<br />
Complex Wastes such as Fuel Reprocessing Wastes<br />
J. Brad Mas<strong>on</strong>, Corey Myers, Studsvik, Inc. (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> THOR fluid bed steam reforming process has been successfully operated for more than 10 years in the USA for<br />
the treatment of low- and intermediate-level radioactive wastes generated by commercial nuclear power plants. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
principle waste stream that has been treated is primarily i<strong>on</strong> exchange resins but various liquids, sludges and solid<br />
organic wastes have also been treated. <str<strong>on</strong>g>The</str<strong>on</strong>g> primary advantages of the THOR process include: (a) maximum volume<br />
reducti<strong>on</strong> <strong>on</strong> the order of 5:1 to 10:1 depending <strong>on</strong> the waste type and waste characteristics; (b) envir<strong>on</strong>mentally<br />
compliant off-gas emissi<strong>on</strong>s, (c) reliable c<strong>on</strong>versi<strong>on</strong> of wastes into mineralized products that are durable and<br />
leach-resistant, and (d) no liquid effluents.<br />
Over the past five years, the THOR process has been adapted for the treatment of more complex wastes including<br />
historic defense wastes, reprocessing wastes, and other wastes associated with the fuel cycle. As part of U. S. Department<br />
of Energy (DOE) envir<strong>on</strong>mental remediati<strong>on</strong> activities, the THOR dual bed steam reforming process was successfully<br />
dem<strong>on</strong>strated to process: Idaho Nati<strong>on</strong>al Laboratory (INL) Sodium-Bearing Waste (SBW); Savannah River Tank 48<br />
High Level Waste (HLW); and Hanford Low Activity Waste (LAW) and Hanford Waste Treatment Plant Sec<strong>on</strong>dary<br />
Waste (WTP SW) liquid slurry simulants. <str<strong>on</strong>g>The</str<strong>on</strong>g> THOR process has been dem<strong>on</strong>strated in pilot plant operati<strong>on</strong>s to<br />
successfully process various simulated liquid, radioactive, nitrate-c<strong>on</strong>taining wastes into envir<strong>on</strong>mentally safe,<br />
leach-resistant solid mineral products. <str<strong>on</strong>g>The</str<strong>on</strong>g> solid products incorporate normally soluble i<strong>on</strong>s, such as sodium, potassium,<br />
cesium, technetium, and sulfate, chloride and fluoride salts into an alkali alumino-silicate mineral matrix that inhibits the<br />
leaching of those i<strong>on</strong>s into the envir<strong>on</strong>ment. <str<strong>on</strong>g>The</str<strong>on</strong>g> solid mineral products produced by the THOR process exhibit durability<br />
and leach resistance characteristics that are superior to borosilicate waste glasses. As a result of this work, a full-scale<br />
THOR process facility is currently under c<strong>on</strong>structi<strong>on</strong> at the DOE’s Idaho site for the treatment of SBW and a full-scale<br />
77
Abstracts<br />
facility is in the final design stage for the DOE’s Savannah River Site for the treatment of Tank 48 Waste.<br />
Recent work has focused <strong>on</strong> the development of new m<strong>on</strong>olithic waste formulati<strong>on</strong>s, the extensi<strong>on</strong> of the THOR<br />
process to new waste streams, and the development of modular THOR processes for niche waste treatment applicati<strong>on</strong>s.<br />
This paper will provide an overview of current THOR projects and summarize the processes and outcomes of the<br />
regulatory and safety reviews that have been necessary for the THOR process to gain acceptance in the USA.<br />
6) 40257 – Phase Behavior and Reverse Micelle Formati<strong>on</strong> in Supercritical CO2 with DTAB and F-pentanol<br />
for Dec<strong>on</strong>taminati<strong>on</strong> of Radioactive Wastes<br />
Kensuke Kurahashi, Osamu Tomioka, Yoshihiro Meguro, JAEA (Japan)<br />
Dec<strong>on</strong>taminati<strong>on</strong> of radioactive wastes is useful for the volume reducti<strong>on</strong> and re-categorizati<strong>on</strong> of them. However, a<br />
large amount of sec<strong>on</strong>dary wastes are often generated from a wet dec<strong>on</strong>taminati<strong>on</strong> using traditi<strong>on</strong>al solvents. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore,<br />
the development of dec<strong>on</strong>taminati<strong>on</strong> method decreasing the sec<strong>on</strong>dary wastes is required. Supercritical CO2 (scCO2),<br />
which is gaseous matter at ordinary c<strong>on</strong>diti<strong>on</strong>s, has the potential to minimize the amount of solvent wastes. However,<br />
neat scCO2 is not suitable for the separati<strong>on</strong> of polar materials, such as metal compounds, because n<strong>on</strong>-polar scCO2<br />
cannot dissolve them. A reverse micelle is a stable aggregate of amphiphilic surfactants surrounding a water pool in a<br />
n<strong>on</strong>-polar solvent. Polar materials can be dissolved in the water pool and dispersed in the n<strong>on</strong>polar solvent. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, the<br />
formati<strong>on</strong> of reverse micelle in scCO2 could increase the availability of scCO2 as a solvent for separati<strong>on</strong> of<br />
radi<strong>on</strong>uclides from radioactive wastes. In the present study, we investigated the reverse micelle formati<strong>on</strong> in scCO2 with<br />
dodeceytrimethylamm<strong>on</strong>ium bromide (DTAB) and 2,2,3,3,4,4,5,5-octafluoro-1-pentanol (Fpentanol). After putting a<br />
mixture of DTAB, F-pentanol and water in a high pressure view cell of 54 cm3 at 45 °C, CO2 was introduced into the<br />
cell slowly. When the mixture was dissolved completely in the scCO2, the pressure was measured as the cloud point<br />
pressure (CPP). When 1.08 mmol DTAB were employed, 13.5 mmol H2O could be dissolved in scCO2 with 6.3 vol%<br />
F-pentanol at 20.9 MPa. Formati<strong>on</strong> of reverse micelles was c<strong>on</strong>firmed by dissolving an aqueous soluti<strong>on</strong> of methyl<br />
orange into the scCO2 with DTAB and water. <str<strong>on</strong>g>The</str<strong>on</strong>g> CPP values were determined for various volume of water. <str<strong>on</strong>g>The</str<strong>on</strong>g> CPP<br />
values increased slowly with an increase of water c<strong>on</strong>centrati<strong>on</strong> in the cell less than 0.35 mol/dm3. <str<strong>on</strong>g>The</str<strong>on</strong>g> increase of water<br />
c<strong>on</strong>centrati<strong>on</strong> led the growth of reverse micelle size, and then the CPP value would rise. On the other hand, the CPP did<br />
not simply increase with the water c<strong>on</strong>centrati<strong>on</strong> more than 0.35 mol/dm3 and a sharp and c<strong>on</strong>cave peak appeared in the<br />
relati<strong>on</strong>ship between the CPP value and the water c<strong>on</strong>centrati<strong>on</strong>. This suggests that the state of water in the scCO2<br />
changed before and after the water c<strong>on</strong>centrati<strong>on</strong> of 0.35 mol/dm3. <str<strong>on</strong>g>The</str<strong>on</strong>g> water c<strong>on</strong>centrati<strong>on</strong> giving the CPP peak<br />
depended <strong>on</strong> the F-pentanol c<strong>on</strong>centrati<strong>on</strong> but was independent of the DTAB c<strong>on</strong>centrati<strong>on</strong>. From this fact, it is expected<br />
that the interacti<strong>on</strong> between F-pentanol and water affects the state of water in the scCO2.<br />
SESSION H7: Performance Assessment Modeling and Parameters<br />
1) 40305 Keynote – Development of a Realistic Repository Performance Assessment Method<br />
Jo<strong>on</strong>h<strong>on</strong>g Ahn, UCB (USA)<br />
Abstract Not Available<br />
2) 40204 – Integrated model for the near field of a repository in granite host-rock. Probabilistic approach<br />
Lara Duro, Alba Valls, Olga Riba, Jordi Bruno, Amphos XXI C<strong>on</strong>sulting S.L.(Spain);<br />
Aurora Martinez-Esparza, ENRESA (Spain)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> applicati<strong>on</strong> of probabilistic approaches to the performance of underground repositories for l<strong>on</strong>g-lived<br />
radioactive waste has received special attenti<strong>on</strong> in the last years. Numerous exercises have been developed in order to<br />
elicit the Probability Distributi<strong>on</strong> Functi<strong>on</strong>s (PDFs) of the several parameters needed for these developments. Several<br />
integrated models allow the implementati<strong>on</strong> of PDFs in the l<strong>on</strong>g-term simulati<strong>on</strong>s needed for Performance Assessment.<br />
In this work we present how the deterministic compartmental model for a repository of high level nuclear waste (HLNW)<br />
located in a crystalline host-rock has been modified to include PDFs for some of the parameters. <str<strong>on</strong>g>The</str<strong>on</strong>g> implementati<strong>on</strong> of<br />
probabilistic approaches gives also informati<strong>on</strong> <strong>on</strong> the most influencing parameter <strong>on</strong> the migrati<strong>on</strong> of the different<br />
radi<strong>on</strong>uclides from a deep repository c<strong>on</strong>cept.<br />
3)� 40017 – Spatial Variability and Parametric Uncertainty in Performance Assessment Models<br />
Osvaldo Pensado, James Mancillas, Scott Painter, Southwest Research Institute (USA);<br />
Yasuo Tomishima, AIST (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> problem of defining an appropriate treatment of distributi<strong>on</strong> functi<strong>on</strong>s (which could represent spatial variability<br />
78
Abstracts<br />
or parametric uncertainty) is examined based <strong>on</strong> a generic performance assessment model for a high-level waste<br />
repository. <str<strong>on</strong>g>The</str<strong>on</strong>g> generic model incorporated source term models available in GoldSim®, the TDRW code for c<strong>on</strong>taminant<br />
transport in sparse fracture networks with a complex fracture-matrix interacti<strong>on</strong> process, and a biosphere dose model<br />
known as BDOSE(TM). Using the GoldSim framework, several M<strong>on</strong>te Carlo sampling approaches and transport<br />
c<strong>on</strong>ceptualizati<strong>on</strong>s were evaluated to explore the effect of various treatments of spatial variability and parametric<br />
uncertainty <strong>on</strong> dose estimates. Results from a model employing a representative source and ensemble-averaged pathway<br />
properties were compared to results from a model allowing for stochastic variati<strong>on</strong> of transport properties al<strong>on</strong>g<br />
streamline segments (i.e., explicit representati<strong>on</strong> of spatial variability within a M<strong>on</strong>te Carlo realizati<strong>on</strong>). We c<strong>on</strong>cluded<br />
that the sampling approach and the definiti<strong>on</strong> of an ensemble representative do influence c<strong>on</strong>sequence estimates. In the<br />
examples analyzed in this paper, approaches c<strong>on</strong>sidering limited variability of a transport resistance parameter al<strong>on</strong>g a<br />
streamline increased the frequency of fast pathways resulting in relatively high dose estimates, while those allowing for<br />
broad variability al<strong>on</strong>g streamlines increased the frequency of "bottlenecks" reducing dose estimates. On this basis,<br />
simplified approaches with limited c<strong>on</strong>siderati<strong>on</strong> of variability may suffice for intended uses of the performance<br />
assessment model, such as evaluati<strong>on</strong> of site safety.<br />
4)� 40203 – Development of a Radiolytic Model for the Alterati<strong>on</strong> of Spent Nuclear Fuel. Incorporati<strong>on</strong> of<br />
n<strong>on</strong>-oxidative matrix dissoluti<strong>on</strong> and hydrogen oxidati<strong>on</strong> inhibiti<strong>on</strong> effect<br />
Lara Duro, Alba Valls, Olga Riba, Jordi Bruno, Amphos XXI C<strong>on</strong>sulting S.L.(Spain);<br />
Aurora Martinez-Esparza, ENRESA (Spain)<br />
In the last years, there have been numerous efforts from nati<strong>on</strong>al waste management agencies to develop models<br />
able to predict the dissoluti<strong>on</strong> behaviour of spent nuclear fuel under interim and/or l<strong>on</strong>g-term storage c<strong>on</strong>diti<strong>on</strong>s. One of<br />
the most evolved models is the so called Matrix Alterati<strong>on</strong> Model (MAM), which is based <strong>on</strong> the radiolytic oxidative<br />
dissoluti<strong>on</strong> of UO2 (Martínez-Esparza et al., 2004) and which has been applied to different experimental results with<br />
certain level of agreement. <str<strong>on</strong>g>The</str<strong>on</strong>g> calibrati<strong>on</strong> of the MAM model in fr<strong>on</strong>t of new experimental data has resulted in the<br />
identificati<strong>on</strong> of some important drawbacks that may result in limited applicability of the model as a predictive tool. In<br />
this work we present the modificati<strong>on</strong>s made to the MAM in order to improve it and expand its range of applicability: -<br />
Incorporati<strong>on</strong> of the n<strong>on</strong> oxidative alterati<strong>on</strong> of the matrix. Ignoring the incorporati<strong>on</strong> of the n<strong>on</strong>-oxidative alterati<strong>on</strong> of<br />
the matrix has proved to be n<strong>on</strong>-c<strong>on</strong>servative over l<strong>on</strong>g-term experiments, resulting in an underestimati<strong>on</strong> of the actual<br />
c<strong>on</strong>centrati<strong>on</strong>s of uranium and radi<strong>on</strong>uclides dissolving c<strong>on</strong>gruently with the matrix (Bruno et al., 2009). <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
incorporati<strong>on</strong> of this mechanism in the MAM has been d<strong>on</strong>e by c<strong>on</strong>sidering the different rates of irradiated and<br />
unirradiated UO2+x determined under reducing c<strong>on</strong>diti<strong>on</strong>s and published in the open scientific literature. <str<strong>on</strong>g>The</str<strong>on</strong>g> modified<br />
MAM is able to reproduce experimental data gathered under a diverse range of experimental c<strong>on</strong>diti<strong>on</strong>s. Incorporati<strong>on</strong> of<br />
the catalytic effect of the surface <strong>on</strong> hydrogen activati<strong>on</strong>. Hydrogen can be generated by radiolysis of water in the vicinity<br />
of the spent nuclear fuel as well as by anaerobic corrosi<strong>on</strong> of metallic comp<strong>on</strong>ents forming <strong>on</strong> the c<strong>on</strong>tainer of the fuel<br />
under storage c<strong>on</strong>diti<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> ability of molecular hydrogen to decrease the rate of dissoluti<strong>on</strong> of the spent fuel matrix<br />
has been attributed to the presence of metallic surfaces in the fuel that can act as catalyst for the activati<strong>on</strong> of molecular<br />
to atomic hydrogen (Carbol et al., 2009). <str<strong>on</strong>g>The</str<strong>on</strong>g> MAM model integrates the H2 inhibiti<strong>on</strong> effect <strong>on</strong> UO2 matrix oxidati<strong>on</strong><br />
by including reacti<strong>on</strong>s between H2 and the UO2 oxidising species, (i.e. c<strong>on</strong>sumpti<strong>on</strong> of oxidants species by H2) (Duro et<br />
al., 2009) but until now the activati<strong>on</strong> of hydrogen <strong>on</strong> the surface of the solids present in the system had not been<br />
implemented. In this work we present the implementati<strong>on</strong> of the heterogeneous activati<strong>on</strong> of hydrogen in order to<br />
reproduce experimental c<strong>on</strong>diti<strong>on</strong>s and couple the predicti<strong>on</strong>s of the l<strong>on</strong>g-term rates of fuel dissoluti<strong>on</strong> of the matrix.<br />
5)� 40172 – Evaluated and Estimated Solubility of Some Elements for Performance Assessment of Geological<br />
Disposal of High-level Radioactive Waste Using Updated Versi<strong>on</strong> of <str<strong>on</strong>g>The</str<strong>on</strong>g>rmodynamic Database<br />
Akira Kitamura, Reisuke Doi, JAEA (Japan); Yasushi Yoshida, Inspecti<strong>on</strong> Development Co., Ltd. (Japan)<br />
A thermodynamic database was established for performance assessment of geological disposal of high-level<br />
radioactive waste (HLW) and TRU waste (equated to l<strong>on</strong>g-lived intermediate level waste) based <strong>on</strong> the thermodynamic<br />
database (JNC-TDB) developed by the Japan Nuclear Cycle Development Institute in 1999. Twenty-five elements<br />
(actinides, fissi<strong>on</strong> products, activated nuclides and their progenies) which were important for the performance assessment<br />
of geological disposal were selected. <str<strong>on</strong>g>The</str<strong>on</strong>g> fundamental plan was in principle based <strong>on</strong> the guidelines established by the<br />
Nuclear Energy Agency (NEA) in the Organisati<strong>on</strong> for Ec<strong>on</strong>omic Co-operati<strong>on</strong> and Development (OECD). Additi<strong>on</strong>al<br />
unique guidelines were established due to a requirement from the performance assessment to select tentative<br />
thermodynamic data obtained from chemical analogues and/or models for elements and species with insufficient<br />
thermodynamic data. <str<strong>on</strong>g>The</str<strong>on</strong>g>rmodynamic data for nickel, selenium, zirc<strong>on</strong>ium, technetium, thorium, uranium, neptunium,<br />
plut<strong>on</strong>ium and americium, which were critically reviewed by the NEA, were taken to our thermodynamic database and<br />
modified. <str<strong>on</strong>g>The</str<strong>on</strong>g>rmodynamic data for cobalt and molybdenum, which were important for the performance assessment of<br />
TRU waste, were newly reviewed, selected and compiled. Some of thermodynamic data for other elements were updated<br />
or modified. All thermodynamic data were extrapolated zero i<strong>on</strong>ic strength using the model called “specific i<strong>on</strong><br />
interacti<strong>on</strong> theory (SIT)”. We tried to assign uncertainty of the selected data as many as possible. Selected<br />
thermodynamic data were compiled as the JAEA’s thermodynamic database (JAEA-TDB), which were available for<br />
some geochemical calculati<strong>on</strong> programs, e.g., PHREEQC. We evaluated and estimated solubility of the 25 elements in<br />
the simulated pore waters established in the sec<strong>on</strong>d progress report (H12) for safety assessment of geological disposal of<br />
79
Abstracts<br />
HLW in Japan using the JAEA-TDB and compared with the solubility values evaluated and estimated using the<br />
JNC-TDB. Furthermore, we tried to establish a technique to determine the solubility limiting solid for all the elements of<br />
interest. It was found that most of the evaluated and estimated solubility values were not changed drastically, but the<br />
solubility values and dominant aqueous species for some elements were changed using the JAEA-TDB, e.g., due to<br />
introducing the formati<strong>on</strong> c<strong>on</strong>stant of polynuclear hydrolysis species of zirc<strong>on</strong>ium and replacing the formati<strong>on</strong> c<strong>on</strong>stant<br />
of mixed carb<strong>on</strong>atohydoxo complexes of thorium. Detail of the comparis<strong>on</strong> and discussi<strong>on</strong> about the evaluated and<br />
estimated solubility values between the JAEA- and the JNC- TDBs will be presented.<br />
6) 40049 – C<strong>on</strong>siderati<strong>on</strong> <strong>on</strong> Soil Origin Carb<strong>on</strong> Transfer to Leafy Vegetables Using Stable Carb<strong>on</strong> Isotope<br />
Ratios<br />
Keiko Tagami, Shigeo Uchida, Nati<strong>on</strong>al Institute of Radiological Sciences (Japan)<br />
From the viewpoint of radiati<strong>on</strong> dose assessment for humans from transuranic waste disposal sites, carb<strong>on</strong>-14<br />
(half-life: 5730 y) in organic forms is thought to be <strong>on</strong>e of the most important radi<strong>on</strong>uclides. Thus, understanding the<br />
C-14 fate in soil-to-crop systems is important since C-14 might transfer from waste disposal sites to crops through the<br />
soil envir<strong>on</strong>ment. It is well known that carb<strong>on</strong> dioxide in the air is the major source for carb<strong>on</strong> assimilati<strong>on</strong> by plants,<br />
thus, carb<strong>on</strong> in soil is less c<strong>on</strong>sidered for plant uptake. Recent results by radiotracer experiments, however, indicated<br />
some c<strong>on</strong>tributi<strong>on</strong> of soil origin carb<strong>on</strong> to plant carb<strong>on</strong>. In this study, we used stable carb<strong>on</strong> isotope ratios (C-13/C-12) in<br />
crop and soil samples. It is well known that C-13 and C-12 are fracti<strong>on</strong>ated in the photosynthesis process at a certain ratio,<br />
depending <strong>on</strong> plant types, i.e. C3, C4 and CAM plants. If all the carb<strong>on</strong> in crops originated <strong>on</strong>ly from the air, the stable<br />
carb<strong>on</strong> isotope ratio would take a c<strong>on</strong>stant value; however, if there were any c<strong>on</strong>tributi<strong>on</strong>s from soil carb<strong>on</strong>, the ratio<br />
would be changed. This approach has been used in our previous study for rice (Tagami and Uchida, 2009) and we tried to<br />
use the method for leafy vegetables. Leafy vegetables were cabbage, Chinese cabbage, lettuce, and leeks, and associated<br />
soil samples were also collected in Japan. Stable carb<strong>on</strong> isotope ratios and total C c<strong>on</strong>centrati<strong>on</strong>s using an elemental<br />
analyzer c<strong>on</strong>nected to an isotope ratio mass spectrometer (<str<strong>on</strong>g>The</str<strong>on</strong>g>rmo Fisher Scientific, Flash EA and Delta V Advantage).<br />
Finally we found that the percentage of soil origin carb<strong>on</strong> to the total plant carb<strong>on</strong> was 2.9%, and the soil-to-plant<br />
transfer factors ranged 0.12-1.1 with an average of 0.5, which was within the previously reported values for radish<br />
(Sheppard et al., 1991).<br />
7) 40050 – Comparis<strong>on</strong> of Soil-to-plant Transfer Factors for Rice and Wheat Grains<br />
Shigeo Uchida, Keiko Tagami, Nati<strong>on</strong>al Institute of Radiological Sciences (Japan)<br />
It is important to understand the behaviors of radi<strong>on</strong>uclides in the agricultural systems since radi<strong>on</strong>uclides enter<br />
humans through ingesti<strong>on</strong> of foods. Critical staple foods are rice and wheat; the former is the dominant staple food crop<br />
in humid tropical and sub-tropical countries across the globe, and the latter is cultivated worldwide. Both are members of<br />
the Poaceae Family; however, they are different in cultivati<strong>on</strong> methods. For example, rice is produced under flooded<br />
c<strong>on</strong>diti<strong>on</strong>s but wheat is grown under upland field c<strong>on</strong>diti<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> difference in cultivati<strong>on</strong> methods may affect plant<br />
uptake of radi<strong>on</strong>uclides from soil. Thus we measured soil-to-grain transfer factors (TFs) of naturally existing elements as<br />
analogues of radi<strong>on</strong>uclides for rice and wheat cultivated in Japan. For this work, we collected from 63 sites for rice and 7<br />
sites for wheat; to the results of wheat, we added 2 barley samples since their cultivati<strong>on</strong> methods were the same. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
elements we measured for TFs were Li, N, Na, Mg, Al, Si, P, K, Ca, Sc, Ti, V, C, Mn, Fe, Co, Ni, Cu, Zn, Ga, As, Se, Br,<br />
Rb, Sr, Y, Zr, Nb, Mo, Ag, Cd, Sn, Sb, I, Cs, Ba, La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, W, Tl, Pb,<br />
Ra, Th and U. Geometric means of TFs of these elements were compared between rice and wheat grains; the tendency<br />
was almost the same and the correlati<strong>on</strong> factor was more than 0.98 by Student’s t-test (p
Abstracts<br />
hydrologic structure of the fault z<strong>on</strong>e. A fourth borehole is planned to penetrate the main fault believed to lie in-between<br />
the holes. <str<strong>on</strong>g>The</str<strong>on</strong>g> main philosophy behind our approach for the hydrologic characterizati<strong>on</strong> of such a complex fractured<br />
system is to let the system take its own average and m<strong>on</strong>itor a l<strong>on</strong>g term behavior instead of collecting a multitude of data<br />
at small length and time scales, or at a discrete fracture scale and to “up-scale,” which is extremely tenuous.<br />
2) 40189 – An attempt to evaluate horiz<strong>on</strong>tal crustal movement by geodetic and geological approach in the<br />
Hor<strong>on</strong>obe area, northern Hokkaido, Japan<br />
Tetsuya Tokiwa, Koichi Asamori, Tadafumi Niizato, Tsuyoshi Nohara, JAEA (Japan);<br />
Yuki Matsuura, Hitachi Zosen Co., Ltd. (Japan); Hideki Kosaka, Kankyo Chishitsu Co., Ltd. (Japan)<br />
In this study, we present the preliminary results for the estimati<strong>on</strong> of a horiz<strong>on</strong>tal crustal movement by using<br />
geodetic and geological approach in the Hor<strong>on</strong>obe area, northern Hokkaido, Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> estimati<strong>on</strong>s have been carried out<br />
by using a GPS data and a geological cross secti<strong>on</strong> obtained by applying balanced-secti<strong>on</strong> method. As results of this<br />
study, both of the shortening rates estimated by GPS data and balanced-secti<strong>on</strong> method indicate several millimeters per<br />
year. Namely, there is no c<strong>on</strong>tradicti<strong>on</strong> between geodetic and geological data, and it is c<strong>on</strong>sidered that Hor<strong>on</strong>obe area is<br />
still situated similar tendency and magnitude of a crustal movement. It is seemingly c<strong>on</strong>sidered that geodetic data is<br />
unhelpful for estimating the l<strong>on</strong>g-term crustal movement, because period of geodetic observati<strong>on</strong>s is a very short.<br />
However, the result of this study indicates that geodetic data provide valuable informati<strong>on</strong> for estimating the l<strong>on</strong>g-term<br />
crustal movement in the area, and it is c<strong>on</strong>sidered that geodetic approach play an important role in improvement of the<br />
credibility of evaluati<strong>on</strong> for predicti<strong>on</strong> of l<strong>on</strong>g-term stability.<br />
3) 40054 – Relati<strong>on</strong>ship between hypocentral distributi<strong>on</strong> and geological structure in the Hor<strong>on</strong>obe area,<br />
northern Hokkaido, Japan<br />
Tetsuya Tokiwa, Koichi Asamori, Naoto Hiraga, Osamu Yamada, Hideharu Yokota, JAEA (Japan);<br />
Hirokazu Moriya, Tohoku University (Japan);<br />
Hikaru Hotta, Itaru Kitamura, C<strong>on</strong>structi<strong>on</strong> Project C<strong>on</strong>sultants, Inc. (Japan)<br />
In this paper, we discuss the relati<strong>on</strong>ship between the accurate hypocentral distributi<strong>on</strong> and three-dimensi<strong>on</strong>al (3-D)<br />
geological structure in and around the Hor<strong>on</strong>obe area in northern Hokkaido, Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> multiplet-clustering analysis was<br />
applied to the 421 micro-earthquakes which occurred from 1 September, 2003 to 30 September, 2007. <str<strong>on</strong>g>The</str<strong>on</strong>g> 3-D<br />
geological structure model was mainly c<strong>on</strong>structed from previous seismic reflecti<strong>on</strong> profiles and borehole data. As a<br />
result of this analysis, although with slight differences in depth between them, the hypocenters were found to be<br />
distributed in the NNW-SSE directi<strong>on</strong> and become deeper from the west toward the east. <str<strong>on</strong>g>The</str<strong>on</strong>g> distributed pattern of the<br />
hypocenters is similar to that of the geological structure. <str<strong>on</strong>g>The</str<strong>on</strong>g>se results indicate that the hypocentral distributi<strong>on</strong> may<br />
represent existence of active z<strong>on</strong>e related to the geological structure, and provide effective informati<strong>on</strong> which can<br />
c<strong>on</strong>tribute to establishing methods for estimating the future evoluti<strong>on</strong> of the geological envir<strong>on</strong>ment.<br />
4) 40062 – Technical know-how for modeling of geological envir<strong>on</strong>ment (1) Overview and groundwater flow<br />
modeling<br />
Hiromitsu Saegusa, Shinji Takeuchi, Keisuke Maekawa, Hideaki Osawa, Takeshi Semba, JAEA (Japan)<br />
It is important for site characterizati<strong>on</strong> projects to manage the decisi<strong>on</strong>-making process with transparency and<br />
traceability and to transfer the technical know-how accumulated during the research and development to the<br />
implementing phase and to future generati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> modeling for a geological envir<strong>on</strong>ment is to be used to synthesize<br />
investigati<strong>on</strong> results. Evaluati<strong>on</strong> of the impact of uncertainties in the model is important to identify and prioritize key<br />
issues for further investigati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, a plan for site characterizati<strong>on</strong> should be made based <strong>on</strong> the results of the<br />
modeling. <str<strong>on</strong>g>The</str<strong>on</strong>g> aim of this study is to support for the planning of initial surface-based site characterizati<strong>on</strong> based <strong>on</strong> the<br />
technical know-how accumulated from the Mizunami Underground Research Laboratory Project and the Hor<strong>on</strong>obe<br />
Underground Research Laboratory Project. <str<strong>on</strong>g>The</str<strong>on</strong>g>se projects are broad scientific studies of the deep geological envir<strong>on</strong>ment<br />
that are a basis for research and development for the geological disposal of high-level radioactive wastes. In this study,<br />
the work-flow of the groundwater flow modeling, which is <strong>on</strong>e of the geological envir<strong>on</strong>ment models, and is to be used<br />
for setting the area for the geological envir<strong>on</strong>ment modeling and for groundwater flow characterizati<strong>on</strong>, and the related<br />
decisi<strong>on</strong>-making process using literature data have been summarized.<br />
5) 40066 – Technical Know-how for Modeling ff Geological Envir<strong>on</strong>ment (2) Geological Modeling<br />
Toshiyuki Matsuoka, Kenji Amano, Hideaki Osawa, Takeshi Semba, JAEA (Japan)<br />
It is important for site characterizati<strong>on</strong> projects to manage the decisi<strong>on</strong>-making process with transparency and<br />
traceability and to transfer the technical know-how developed and accumulated during the research and development to<br />
the implementing phase as well as to future generati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> modeling of a geological envir<strong>on</strong>ment supports efforts to<br />
clarify the degree of understanding regarding that geological envir<strong>on</strong>ment, including uncertainty. Evaluati<strong>on</strong> of the<br />
81
Abstracts<br />
impact of uncertainties in a geological envir<strong>on</strong>ment model is important to identify and prioritize key issues for further<br />
investigati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, a plan for site characterizati<strong>on</strong> should be made based <strong>on</strong> the results of the modeling. <str<strong>on</strong>g>The</str<strong>on</strong>g> aim of<br />
this study is to support the planning of initial surface-based site characterizati<strong>on</strong> based <strong>on</strong> the technical know-how<br />
accumulated from the Mizunami Underground Research Laboratory Project and the Hor<strong>on</strong>obe Underground Research<br />
Laboratory Project. <str<strong>on</strong>g>The</str<strong>on</strong>g>se projects are broad scientific studies of the deep geological envir<strong>on</strong>ment that are a basis for<br />
research and development for the geological disposal of high-level radioactive wastes. In this study, the work-flow<br />
followed in developing the geological model, <strong>on</strong>e of the geological envir<strong>on</strong>ment models, and the related technical<br />
know-how acquired from literature data have been summarized.<br />
6) 40039 – <str<strong>on</strong>g>The</str<strong>on</strong>g> l<strong>on</strong>g-term stability of geological envir<strong>on</strong>ments in the various rock types in Japan from the<br />
perspective of uranium mineralizati<strong>on</strong><br />
Eiji Sasao, JAEA (Japan)<br />
L<strong>on</strong>g-term stability of the geological envir<strong>on</strong>ment is <strong>on</strong>e of the important keys for deep geological disposal of<br />
high-level radioactive waste in the Japanese Islands due to their locati<strong>on</strong> in a tect<strong>on</strong>ically active island-arc. Uranium<br />
occurrences in Japan have been subjected to many geological processes inherent to the island-arc setting. Geological<br />
envir<strong>on</strong>ments associated with uranium mineralizati<strong>on</strong> are c<strong>on</strong>sidered favorable for HLW disposal, because uranium<br />
mineralizati<strong>on</strong> is c<strong>on</strong>sidered a natural analogue of the radi<strong>on</strong>uclides in HLW. Studies <strong>on</strong> the l<strong>on</strong>g-term stability of the<br />
uranium mineralizati<strong>on</strong> in Japan can be instructive as these could provide useful informati<strong>on</strong> <strong>on</strong> the l<strong>on</strong>g-term stability of<br />
the geological envir<strong>on</strong>ment. Informati<strong>on</strong> <strong>on</strong> host rock and mode of occurrence of uranium mineralizati<strong>on</strong> was compiled<br />
from published data. <str<strong>on</strong>g>The</str<strong>on</strong>g> mineralizati<strong>on</strong> occurs in these types of deposits, i.e., sedimentary formati<strong>on</strong>s, associati<strong>on</strong> with<br />
metallic ore mineralizati<strong>on</strong> of magmatic origin and stratiform manganese mineralizati<strong>on</strong>, pegmatite, and alluvial placer<br />
deposit. <str<strong>on</strong>g>The</str<strong>on</strong>g> mineralizati<strong>on</strong> occurs in various geological settings in Japan. This fact suggests that geological<br />
envir<strong>on</strong>ments suitable for geological isolati<strong>on</strong> are widely distributed in the Japanese Islands, despite their locati<strong>on</strong> in a<br />
geologically active area. This study will support building c<strong>on</strong>fidence in HLW disposal in the Japanese Islands.<br />
SESSION D5: Measurement and Estimati<strong>on</strong><br />
1) 40045 – Improvement of Radioactivity Inventory Evaluati<strong>on</strong> Procedure In Preparatory Tasks for<br />
Decommissi<strong>on</strong>ing<br />
Ken-ichi Tanaka, Hidenori Tanabe, Hideaki Ichige, JAPC (Japan)<br />
Preparatory tasks for decommissi<strong>on</strong>ing of nuclear power plant start with radiological characterizati<strong>on</strong>. Residual<br />
radioactivity inventory evaluati<strong>on</strong> is a main part of the characterizati<strong>on</strong>. Reliable informati<strong>on</strong> <strong>on</strong> the inventory is<br />
important for specificati<strong>on</strong> for decommissi<strong>on</strong>ing plan. Japan Atomic Power Company (JAPC) has already started these<br />
tasks for Tsuruga Nuclear Power Plant Unit 1 (TS-1). We can optimize decommissi<strong>on</strong>ing plan using the informati<strong>on</strong>. To<br />
obtain the reliable informati<strong>on</strong>, we improved an evaluati<strong>on</strong> procedure. <str<strong>on</strong>g>The</str<strong>on</strong>g> procedure is divided into two main steps. First<br />
step is neutr<strong>on</strong> flux distributi<strong>on</strong> calculati<strong>on</strong> and sec<strong>on</strong>d <strong>on</strong>e is radioactivity distributi<strong>on</strong> calculati<strong>on</strong>. Radioactivity<br />
distributi<strong>on</strong> is calculated using neutr<strong>on</strong> flux distributi<strong>on</strong>. In this work, we improved the evaluati<strong>on</strong> procedure to obtain the<br />
reliable informati<strong>on</strong> <strong>on</strong> the inventory Because of the limitati<strong>on</strong> of computer resource, two-dimensi<strong>on</strong> (2D) approximati<strong>on</strong><br />
model was applied to radioactivity distributi<strong>on</strong> around Reactor Pressure Vessel (RPV). We can calculate reliable 2D<br />
neutr<strong>on</strong> flux distributi<strong>on</strong> by having better understanding of neutr<strong>on</strong> transport phenomena. Neutr<strong>on</strong> flux was measured at<br />
30 locati<strong>on</strong>s in TS-1 Primary C<strong>on</strong>tainment Vessel (PCV) using activati<strong>on</strong> foils. And in order to understand the neutr<strong>on</strong><br />
transport phenomen<strong>on</strong> inside the PCV, we also calculated neutr<strong>on</strong> flux distributi<strong>on</strong> with the three-dimensi<strong>on</strong>al (3D)<br />
discrete ordinates method calculati<strong>on</strong> (Sn) code. By c<strong>on</strong>siderati<strong>on</strong> about the result of the measurement and 3D calculati<strong>on</strong>,<br />
we could understand the characteristics of the neutr<strong>on</strong> flux distributi<strong>on</strong> inside the PCV. To simulate the neutr<strong>on</strong> flux<br />
distributi<strong>on</strong> well with 2D Sn code, neutr<strong>on</strong> flux behaviors inside the PCV had been investigated with referencing the<br />
measurement values and with observing calculated 3D neutr<strong>on</strong> flux distributi<strong>on</strong>. 2D calculati<strong>on</strong> model had been modified<br />
repeatedly until reliable calculati<strong>on</strong> result was provided. After several model modificati<strong>on</strong>s, the reliable 2D calculati<strong>on</strong><br />
was accomplished and important neutr<strong>on</strong> transport phenomena that are necessary to simulate the neutr<strong>on</strong> flux distributi<strong>on</strong><br />
well was understood. Network-parallel-computing technique was applied to radioactivity distributi<strong>on</strong> calculati<strong>on</strong>. Using<br />
this technique, we could calculate radioactivity at all space mesh points that were used with 2D Sn code and we obtained<br />
the radioactivity distributi<strong>on</strong>. By using this distributi<strong>on</strong>, we can estimate a quantity of radioactivity around RPV more<br />
accurately and optimize dismantling designs.<br />
2) 40202 – Verificati<strong>on</strong> of Source Term Analysis System for Decommissi<strong>on</strong>ing Wastes from CANDU Reactor<br />
D<strong>on</strong>g-Keun Cho, Gwang-Min SUN, J<strong>on</strong>gw<strong>on</strong> Choi, KAERI (Korea Rep.);<br />
D<strong>on</strong>ghyeun Hwang, Hak-Soo Kim, Tae-W<strong>on</strong> Hwang, KHNP (Korea Rep.)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>re are now twenty commercial nuclear power reactors operating as of May 2010 in South Korea. As nuclear<br />
capacity becomes higher and installati<strong>on</strong>s age, the Korean government and industry have launched R&D to estimate<br />
82
Abstracts<br />
appropriate decommissi<strong>on</strong>ing costs of power reactors. In this paper, MCNP/ORIGEN2 code system which is being<br />
developed as a source term evaluati<strong>on</strong> tool was verified by comparing the estimated nuclide inventory from<br />
MCNP/ORIGEN2 simulati<strong>on</strong> with the measured nuclide inventory from chemical assay in an irradiated pressure tube<br />
discharged from Wols<strong>on</strong>g Unit 1 in 1994. Equilibrium core model of Wolsoung unit 1 was used as a neutr<strong>on</strong> source to<br />
activate in-core and ex-core structural comp<strong>on</strong>ents. As a result, the estimated values from the analysis system agreed with<br />
measured data within 20% difference. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, it can be c<strong>on</strong>cluded that MCNP/ORIGEN system could be a reliable<br />
tool to estimate source terms of decommissi<strong>on</strong>ing wastes from CANDU reactor, although this system assumes c<strong>on</strong>stant<br />
flux irradiati<strong>on</strong> and snapshot equilibrium core model as a reference core.<br />
3) 40294 – Evaluati<strong>on</strong> of <str<strong>on</strong>g>The</str<strong>on</strong>g> Activated Radioactivity of Turbine Equipments in BWR<br />
Masato Watanabe, Mot<strong>on</strong>ori Nakagami, Chubu Electric Power Co., Inc. (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> equipments in the main steam system under the plant operati<strong>on</strong> were irradiated by the neutr<strong>on</strong> emitted from<br />
N-17 which is produced by (n,p) reacti<strong>on</strong> of the coolant in Boiling Water Reactor (BWR) plants. However, <strong>on</strong>ly few<br />
measures, regarding the radioactive c<strong>on</strong>centrati<strong>on</strong> of N-17 in the main steam system of BWR, were indicated up to now.<br />
In this study, the radioactive c<strong>on</strong>centrati<strong>on</strong> of N-17 in the main steam system of the advanced boiling water reactor<br />
(ABWR) plant, Hamaoka unit-5, is evaluated by the neutr<strong>on</strong> flux measurements and calculati<strong>on</strong>s.<br />
It was found that the c<strong>on</strong>centrati<strong>on</strong> of N-17 at the reactor pressure vessel outlet nozzle of the main steam pipe is<br />
approximately 3 Bq/cm3. It turns out that the c<strong>on</strong>centrati<strong>on</strong> has small dependency <strong>on</strong> nuclear thermal power and that it is<br />
relatively comm<strong>on</strong> am<strong>on</strong>g the BWR plants.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>n, the activated activities of turbine equipments and pipes in the main steam system are evaluated by using the<br />
measured radioactive c<strong>on</strong>centrati<strong>on</strong> of N-17. <str<strong>on</strong>g>The</str<strong>on</strong>g> activities of the equipments in the main steam system are relatively<br />
very low level.<br />
4) 40014 – Optimizati<strong>on</strong> of Quantitative Waste Volume Determinati<strong>on</strong> Technique for Hanford Waste Tank<br />
Closure<br />
Yi Su, David L. M<strong>on</strong>ts, Ping-Rey Jang, Zhiling L<strong>on</strong>g, Walter P. Okhuysen, Olin P. Nort<strong>on</strong>, Lawrence L. Gresham,<br />
Jeffrey S. Lindner, Mississippi State University (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and<br />
double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is<br />
left in a given waste tank and the uncertainty with which that volume is known.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a<br />
quantitative in-tank imaging system based <strong>on</strong> Fourier Transform Profilometry, FTP. FTP is a n<strong>on</strong>-c<strong>on</strong>tact, 3-D shape<br />
measurement technique. By projecting a fringe pattern <strong>on</strong>to a target surface and observing its deformati<strong>on</strong> due to surface<br />
irregularities from a different view angle, FTP is capable of determining the height (depth) distributi<strong>on</strong> (and hence<br />
volume distributi<strong>on</strong>) of the target surface, thus reproducing the profile of the target accurately under a wide variety of<br />
c<strong>on</strong>diti<strong>on</strong>s. Hence FTP has the potential to be utilized for quantitative determinati<strong>on</strong> of residual wastes within Hanford<br />
waste tanks. In this paper, efforts to characterize the accuracy and precisi<strong>on</strong> of quantitative volume determinati<strong>on</strong> using<br />
FTP and the use of these results to optimize the FTP system for deployment within Hanford waste tanks are described.<br />
5) 40120 – Implementati<strong>on</strong> of Decommissi<strong>on</strong>ing Materials C<strong>on</strong>diti<strong>on</strong>al Clearance Process to the OMEGA<br />
Calculati<strong>on</strong> Code<br />
Matej Zachar, Vladimir Necas, Slovak University of Technology (Slovakia);<br />
Vladimir Daniska, DECONTA a.s. (Slovakia)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> activities performed during nuclear installati<strong>on</strong> decommissi<strong>on</strong>ing process inevitably lead to the producti<strong>on</strong> of<br />
large amount of radioactive material to be managed. Significant part of materials has such low radioactivity level that<br />
allows them to be released to the envir<strong>on</strong>ment without any restricti<strong>on</strong> for further use. On the other hand, for materials<br />
with radioactivity slightly above the defined unc<strong>on</strong>diti<strong>on</strong>al clearance level, there is a possibility to release them<br />
c<strong>on</strong>diti<strong>on</strong>ally for a specific purpose in accordance with developed scenario assuring that radiati<strong>on</strong> exposure limits for<br />
populati<strong>on</strong> not to be exceeded. <str<strong>on</strong>g>The</str<strong>on</strong>g> procedure of managing such decommissi<strong>on</strong>ing materials, menti<strong>on</strong>ed above, could<br />
lead to recycling and reuse of more solid materials and to save the radioactive waste repository volume. In the paper an<br />
implementati<strong>on</strong> of the process of c<strong>on</strong>diti<strong>on</strong>al release to the OMEGA Code is analyzed in details; the Code is used for<br />
calculati<strong>on</strong> of decommissi<strong>on</strong>ing parameters. <str<strong>on</strong>g>The</str<strong>on</strong>g> analytical approach in the material parameters assessment, firstly,<br />
assumes a definiti<strong>on</strong> of radiological limit c<strong>on</strong>diti<strong>on</strong>s, based <strong>on</strong> the evaluati<strong>on</strong> of possible scenarios for c<strong>on</strong>diti<strong>on</strong>ally<br />
released materials, and their applicati<strong>on</strong> to appropriate sorter type in existing material and radioactivity flow system.<br />
Other calculati<strong>on</strong> procedures with relevant technological or ec<strong>on</strong>omical parameters, mathematically describing e.g. final<br />
radiati<strong>on</strong> m<strong>on</strong>itoring or transport outside the locality, are applied to the OMEGA Code in the next step. Together with<br />
limits, new procedures creating independent material stream allow evaluati<strong>on</strong> of c<strong>on</strong>diti<strong>on</strong>al material release process<br />
during decommissi<strong>on</strong>ing. Model calculati<strong>on</strong>s evaluating various scenarios with different input parameters and<br />
c<strong>on</strong>sidering c<strong>on</strong>diti<strong>on</strong>al release of materials to the envir<strong>on</strong>ment are performed to verify the implemented methodology.<br />
Output parameters and results of the model assessment are presented, discussed and c<strong>on</strong>cluded in the final part of the<br />
83
paper.<br />
Abstracts<br />
6) 40183 – Quantitative determinati<strong>on</strong> of the initial comp<strong>on</strong>ents in the activated pressure tubes of the Wols<strong>on</strong>g<br />
1st CANDU reactor<br />
Gwang-Min Sun, D<strong>on</strong>g-Keun Cho, KAERI (Korea Rep.)<br />
When the end of the original lifespan is coming for the Wols<strong>on</strong>g 1st CANDU reactor in Korea, decommissi<strong>on</strong>ing<br />
has been <strong>on</strong>e of the largest issues requiring large expense, which is facing the nuclear industry and the government.<br />
Korean government intends to provide public funds, which have been accumulated using a porti<strong>on</strong> of the electrical<br />
charge, to dismantle reactors when the time comes. <str<strong>on</strong>g>The</str<strong>on</strong>g> radioactive sources in the c<strong>on</strong>structi<strong>on</strong> stuffs and comp<strong>on</strong>ents of<br />
reactor such as pressure tube, steam generator and so <strong>on</strong> must be evaluated for the estimati<strong>on</strong> of appropriate expense for<br />
the decommissi<strong>on</strong>ing. <str<strong>on</strong>g>The</str<strong>on</strong>g> overall objective of this study is to c<strong>on</strong>firm the methods for the elemental or isotopic analysis<br />
of the pressure tube samples from nuclear reactor in order to make possible the reliable applicati<strong>on</strong> of the methods to the<br />
case of the Wols<strong>on</strong>g 1st CANDU reactor. To achieve this objective we need to categorize the methods into two groups<br />
taking into account the applicability of the methods to the target we have interests in. <str<strong>on</strong>g>The</str<strong>on</strong>g> radiochemical analytical<br />
methods such as liquid scintillati<strong>on</strong> counting, X-ray spectroscopy and normal gamma-ray spectroscopy and so <strong>on</strong> to<br />
measure the trace isotopic beings such as 60Co, 94Nb, 54Mn, 55Fe, 59Ni, 63Ni and so <strong>on</strong>. Elemental analysis methods<br />
such as instrumental neutr<strong>on</strong> activati<strong>on</strong> analysis (INAA) and prompt gamma activati<strong>on</strong> analysis (PGAA) to measure the<br />
initial compositi<strong>on</strong>s of the samples. In present work, we will deal with INAA and PGAA to determine an elemental<br />
compositi<strong>on</strong> of the pressure tube. <str<strong>on</strong>g>The</str<strong>on</strong>g> prepared samples are irradiated in the NAA #1, NAA #2 and SNU-KAERI PGAA<br />
facility of the HANARO research reactor in Korea Atomic Energy Research Institute. Because the samples are from<br />
pressure tube of reactor, the most abundant element must be ir<strong>on</strong> and other elements can be determined relative to the<br />
ir<strong>on</strong> c<strong>on</strong>tent. From this idea, we determined the initial elemental compositi<strong>on</strong> of the samples through two-step procedure.<br />
For the absolute determinati<strong>on</strong> of ir<strong>on</strong> c<strong>on</strong>tent in the sample, the count rate must be calibrated according to the ir<strong>on</strong><br />
elemental c<strong>on</strong>tent as shown in figure 8 where the slope of the line is a specific count rate or analytical sensitivity given in<br />
cps/?g. <str<strong>on</strong>g>The</str<strong>on</strong>g> relative mass of other elements in the samples were determined by using a k0-standardizati<strong>on</strong> method which<br />
has been usually used in the INAA and also in the PGAA.<br />
SESSION R3: ER Techniques<br />
1) 40286 – Sequential Extracti<strong>on</strong> and Determinati<strong>on</strong> of Depleted Uranium in the Presence of Natural Uranium in<br />
Envir<strong>on</strong>mental Soil samples by ICP-MS<br />
Mohamed Amr, Alaa E. Negmeldin, Khalid Al-Saad, A. T. Al-Kinani, Qatar University (Qatar);<br />
A. I. Helal, Atomic Energy Authority (Qatar)<br />
Determinati<strong>on</strong> of depleted uranium (DU) in the presence of natural uranium (NU) by inductively coupled plasma<br />
mass spectrometry (ICP-MS) was applied <strong>on</strong> envir<strong>on</strong>mental soil samples collected from Qatar. <str<strong>on</strong>g>The</str<strong>on</strong>g> soils were artificially<br />
spiked by soaking them in a mixture of DU and NU. <str<strong>on</strong>g>The</str<strong>on</strong>g> detecti<strong>on</strong> limit of 235U and 238U isotopes were 141 ppt and<br />
1.28 ppt, respectively. It was observed from sequential experiment that uranium was brought into soluti<strong>on</strong> mainly<br />
appeared at steps for dilute acid-soluble, carb<strong>on</strong>ate-bound and organic matter-bound species. Little redistributi<strong>on</strong> was<br />
observed at steps for exchangeable and Fe-Mn oxide-bound species.<br />
2) 40096 – Determinati<strong>on</strong> of Envir<strong>on</strong>mental Uranium C<strong>on</strong>centrati<strong>on</strong> by Utilizing Gamma-ray Emissi<strong>on</strong> from the<br />
Progeny Radi<strong>on</strong>uclides<br />
Tadao Tanaka, Taro Shimada, Takenori Sukegawa, JAEA (Japan); Takeshi Ito, Japan ATOX Co., Ltd. (Japan)<br />
Nuclear facility sites such as enrichment plant and fabricati<strong>on</strong> plant are allowed to be released from nuclear safety<br />
regulati<strong>on</strong>s after the plants are decommissi<strong>on</strong>ed. <str<strong>on</strong>g>The</str<strong>on</strong>g> sites are necessary to c<strong>on</strong>firm to be dec<strong>on</strong>taminated, prior to be<br />
released.<br />
Gamma-ray emissi<strong>on</strong> from the progeny radi<strong>on</strong>uclides of uranium such as Th-234, Pa234m, Ra-226 has been utilized<br />
for the determinati<strong>on</strong> of uranium c<strong>on</strong>centrati<strong>on</strong> in soils. Gamma-ray emissi<strong>on</strong> radi<strong>on</strong>uclides occurring in spacious areas<br />
of land was often measured by the in-situ method with portable germanium semic<strong>on</strong>ductor detector (portable Ge<br />
detector), to c<strong>on</strong>firm that there is no significant gamma-ray emissi<strong>on</strong> radi<strong>on</strong>uclides distributed in the vast land areas. In<br />
the present study, we proposed a determinati<strong>on</strong> method for U-238 c<strong>on</strong>centrati<strong>on</strong> of background level in envir<strong>on</strong>ment and<br />
for probate of vast site areas, in which the gamma-ray radioactivities from Th-234, Pa-234m, Ra-226 are measured with<br />
the portable Ge detector.<br />
Validity of the estimati<strong>on</strong> method of U-238 c<strong>on</strong>centrati<strong>on</strong> from the progeny radi<strong>on</strong>uclides was examined by the<br />
comparis<strong>on</strong> between the U-238 c<strong>on</strong>centrati<strong>on</strong> estimated by the in-situ method with portable Ge detector and that directly<br />
measured by ICP-MS. <str<strong>on</strong>g>The</str<strong>on</strong>g> U-238 c<strong>on</strong>centrati<strong>on</strong> by the in-situ method was estimated from peak counting rate at 63 keV<br />
of the gamma-ray emissi<strong>on</strong> corresp<strong>on</strong>ding to Th-234 and from that at 186 keV corresp<strong>on</strong>ding to Ra226. <str<strong>on</strong>g>The</str<strong>on</strong>g> estimated<br />
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Abstracts<br />
U-238 c<strong>on</strong>centrati<strong>on</strong> was in the order of 0.01 Bq/g in radioactive c<strong>on</strong>centrati<strong>on</strong>, and was in comparable level with the<br />
c<strong>on</strong>centrati<strong>on</strong>s decided by the ICP-MS.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> determinati<strong>on</strong> method of U-238 c<strong>on</strong>centrati<strong>on</strong> from the progeny radi<strong>on</strong>uclides was applied to the site<br />
c<strong>on</strong>taminated by low-level uranium resourced from an uranium handling facility. <str<strong>on</strong>g>The</str<strong>on</strong>g> U-238 c<strong>on</strong>centrati<strong>on</strong> could be<br />
determined from the peak counting rates corresp<strong>on</strong>ding to Th-234 and Ra-226. <str<strong>on</strong>g>The</str<strong>on</strong>g> proposed method utilizing<br />
gamma-ray radioactivities from the progeny radi<strong>on</strong>uclides may be available for the U-238 c<strong>on</strong>centrati<strong>on</strong> determinati<strong>on</strong> in<br />
vast land areas.<br />
3) 40170 – Natural Radioactivity Levels And Gamma-Ray Dose Rate In Soil And Transfer Of Radi<strong>on</strong>uclides<br />
From Soil To Vegetati<strong>on</strong> Of Some Northern Area Of Pakistan Using Gamma-Ray Spectrometry<br />
Muhammad Ismail, Hasan M.Khan, Peshawar University (Pakistan); Khalid Khan, Pinstech Islamabad (Pakistan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> analysis of gamma emitters natural radi<strong>on</strong>uclides i.e. 226Ra, 232Th and 40K has been carried out in soil,<br />
vegetati<strong>on</strong>, vegetable and water samples collected from some Northern area of Pakistan, using gamma-ray spectrometry.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> gamma-ray spectrometry was carried out using high purity Germanium (HPGe) detector coupled with a computer<br />
based high resoluti<strong>on</strong> multi channel analyzer. <str<strong>on</strong>g>The</str<strong>on</strong>g> activities c<strong>on</strong>centrati<strong>on</strong>s in soil ranged from 24.7 to 78.5 Bq kg-1, 21.7<br />
to 75.3 Bq kg-1 and 298.5 to 570.8 Bq kg-1 for 226Ra, 232Th and 40K with the mean value of 42.1, 43.3, 9.5 and 418.3<br />
Bq kg-1, respectively. <str<strong>on</strong>g>The</str<strong>on</strong>g> radium equivalent activity, internal and external hazard indices have mean values of 136.11<br />
Bq kg-1, 0.48 and 0.37, respectively. <str<strong>on</strong>g>The</str<strong>on</strong>g> mean values of outdoor and indoor absorbed dose rate in air were found 64.61<br />
nGy.h-1 and 77.54 nGy.h-1, respectively. In the present analysis, 40K was the major radi<strong>on</strong>uclide present in soil,<br />
vegetati<strong>on</strong>, fruit and vegetable samples. <str<strong>on</strong>g>The</str<strong>on</strong>g> activity c<strong>on</strong>centrati<strong>on</strong> of 40K in vegetati<strong>on</strong> sample varied from 646.6 Bq<br />
kg-1 to 869.6 Bq kg-1 <strong>on</strong> dry weight basis. However, the activity c<strong>on</strong>centrati<strong>on</strong> of 40K in fruit and vegetable samples<br />
varied from 34.0 Bq kg-1 to 123.3 Bq kg-1 <strong>on</strong> fresh weight basis. <str<strong>on</strong>g>The</str<strong>on</strong>g> transfer factors of these radi<strong>on</strong>uclides from soil to<br />
vegetati<strong>on</strong> and vegetable were also studied. <str<strong>on</strong>g>The</str<strong>on</strong>g> analysis of water samples showed activities c<strong>on</strong>centrati<strong>on</strong>s for all<br />
radi<strong>on</strong>uclides below detecti<strong>on</strong> limit. <str<strong>on</strong>g>The</str<strong>on</strong>g> activities c<strong>on</strong>centrati<strong>on</strong>s of radi<strong>on</strong>uclides found in all samples during the current<br />
investigati<strong>on</strong> were nominal. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore they are not associated with any potential source of health hazard to the general<br />
public.<br />
4) 40034 – Effect of Fertilizer and Soil Amendments <strong>on</strong> Extracti<strong>on</strong> Yields of Radioiodine and Radiocesium in Soil<br />
Hirofumi Tsukada, Akira Takeda, Shunichi Hisamatsu, Institute for Envir<strong>on</strong>mental Sciences (Japan)<br />
Mobile fracti<strong>on</strong> of radi<strong>on</strong>uclides in a soil, which is water-extractable and exchangeable, is important informati<strong>on</strong> for<br />
remediati<strong>on</strong> in the terrestrial envir<strong>on</strong>ment. Radioiodine and radiocesium derived from atmospheric nuclear weap<strong>on</strong>s tests<br />
and released from nuclear facilities are major radi<strong>on</strong>uclides for the assessment of radiati<strong>on</strong> exposure to the public. In the<br />
present study, the effects of fertilizer and soil amendments <strong>on</strong> the extracti<strong>on</strong> yields of radioiodine and radiocesium in a<br />
soil were investigated. A surface soil (Andosol) was collected from grassland in Aomori, Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> soil was mixed with<br />
the following amendments: Chemical fertilizer (NH4, PO4, K): 0.24 mg N, 0.16 mg P2O5, or 0.16 mg K2O per g soil,<br />
Compost (rice straw mixed with cattle feces): 50 mg per g soil, and Clay mineral (illite, kaolinite, m<strong>on</strong>tmorill<strong>on</strong>ite,<br />
sericite, vermiculite, zeolite): 20 mg per g soil.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>y were mixed and then 10 kBq of 125I or 137Cs was added to <strong>on</strong>e g of the soil sample. <str<strong>on</strong>g>The</str<strong>on</strong>g>y were stored in an<br />
artificial climate chamber, and a wetting-and-drying treatment was repeated by adding <strong>on</strong>e ml of dei<strong>on</strong>ized water every 2<br />
weeks. <str<strong>on</strong>g>The</str<strong>on</strong>g> extracti<strong>on</strong> yields of 125I with water, and 137Cs with water or 1 M amm<strong>on</strong>ium acetate soluti<strong>on</strong> were<br />
determined at 10, 30 and 120 d after additi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> extracti<strong>on</strong> yield of 125I in the soil without amendment (the c<strong>on</strong>trol<br />
sample) decreased to 4% of the added amount at 120 d after additi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> extracti<strong>on</strong> yield of 125I in the soil mixed with<br />
the compost at 10 and 30 d after additi<strong>on</strong> was higher than that in each c<strong>on</strong>trol soil, and the difference was accompanied<br />
by an increase of the dissolved organic carb<strong>on</strong> c<strong>on</strong>tent in the water extract of the compost applicati<strong>on</strong> soil. <str<strong>on</strong>g>The</str<strong>on</strong>g> extracti<strong>on</strong><br />
yield of 125I in the soil mixed with the m<strong>on</strong>tmorill<strong>on</strong>ite was higher than that in the c<strong>on</strong>trol soil through the aging period.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> extracti<strong>on</strong> yield of 137Cs in the c<strong>on</strong>trol soil with water and amm<strong>on</strong>ium acetate decreased to 0.12% and 32% at 120 d<br />
after additi<strong>on</strong>, respectively. <str<strong>on</strong>g>The</str<strong>on</strong>g> extracti<strong>on</strong> of 137Cs with water was enhanced by the applicati<strong>on</strong> of the nitrogen fertilizer<br />
and the compost, whereas that was depressed by the applicati<strong>on</strong> of the clay minerals. <str<strong>on</strong>g>The</str<strong>on</strong>g> extracti<strong>on</strong> of 137Cs with<br />
amm<strong>on</strong>ium acetate was also depressed by the clay minerals, and this may be caused by the large cesium intercepti<strong>on</strong> sites<br />
in the clay minerals. It was clear that the mobile fracti<strong>on</strong>s of radioiodine and radiocesium in the soil were changed by<br />
several treatments. This work was c<strong>on</strong>ducted under c<strong>on</strong>tract with the Aomori Prefectural Government, Japan.<br />
5) 40246 – Impact of Mobile-Immobile Water Domains <strong>on</strong> the Retenti<strong>on</strong> of Technetium (Tc-99) in the Vadose<br />
Z<strong>on</strong>e<br />
Danielle Jansik, Dawn Wellman, Elsa Cordova, PNNL (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> transport of technetium (Tc-99), like many other radi<strong>on</strong>uclides, is of interest due to the potential for human<br />
exposure and impact <strong>on</strong> ecosystems. Technetium has been released to the envir<strong>on</strong>ment through nuclear power producti<strong>on</strong><br />
and nuclear fuel processing; as a result, further spreading of Tc-99 is a c<strong>on</strong>cern at DOE sites across the US. Specifically,<br />
technetium is a c<strong>on</strong>taminant of c<strong>on</strong>cern at Hanford, Savannah River, Idaho, and Oak Ridge Nati<strong>on</strong>al Laboratory. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
current body of work c<strong>on</strong>ducted <strong>on</strong> Tc-99 has provided a wealth of informati<strong>on</strong> regarding the redox relati<strong>on</strong>ships,<br />
85
Abstracts<br />
sorpti<strong>on</strong>, solubility, and stability of the mineral phases (Artinger et al., 2003; Beals and Hayes, 1995; Cui and Eriksen,<br />
1996b; Gu and Schulz, 1991; Jaisi et al., 2009; Keith-Roach et al., 2003; Kumar et al., 2007), however little work has<br />
been c<strong>on</strong>ducted <strong>on</strong> the physical transport of the highly soluble pertechnetate oxyani<strong>on</strong>, in the subsurface. Current<br />
c<strong>on</strong>ceptual models do not explain the persistence and presence of the ani<strong>on</strong> in deep vadose z<strong>on</strong>e envir<strong>on</strong>ments such as the<br />
Hanford site. In an oxic reducing envir<strong>on</strong>ment with low organic c<strong>on</strong>tent the residence time of technetium is the soil<br />
would be expected to be near low, due to its low sorpti<strong>on</strong>. Surprisingly, nearly 50 years following the release of<br />
c<strong>on</strong>taminati<strong>on</strong> into the site, much of the element has persisted in the subsurface, in its most mobile form. Using an<br />
Unsaturated Flow Apparatus (UFA) we have c<strong>on</strong>ducted a series of experiments to examine the impact of<br />
mobile-immobile domains <strong>on</strong> the transport of Tc-99. By varying sand/silt ratios and saturati<strong>on</strong>s we examined how<br />
changes in pore geometry and moisture c<strong>on</strong>tent impact the transport of Tc-99 within our experimental system. Results<br />
dem<strong>on</strong>strating the impact of sediment texture pore morphology, and soil moisture c<strong>on</strong>tent <strong>on</strong> physical impediments to<br />
Tc-99 transport will be presented.<br />
6) 40207 – Nano Technologies for Envir<strong>on</strong>mental Remediati<strong>on</strong><br />
Harch Gill, Lehigh Nanotech (USA)<br />
This paper presents two innovative nanotechnology products, NanoFeTM and Nano-OxTM, that have been<br />
successfully used for the in-situ treatment of soil and groundwater. NanoFeTM c<strong>on</strong>sists primarily of submicr<strong>on</strong> (
Abstracts<br />
SESSION L7: Storage and Disposal Facility<br />
1) 40095 – Design, Licensing and Commissi<strong>on</strong>ing Activities for the Waste Storage Facility to Manage the Waste<br />
Streams from Retubing of Wols<strong>on</strong>g-1 CANDU 600 MW Nuclear Generating Stati<strong>on</strong> in South Korea<br />
Nikos P<strong>on</strong>tikakis, John Ballantine, Shar<strong>on</strong> Hugh, Joulien Moussalam, AECL (Canada)<br />
Until recently, the operating license for the Waste Storage Facility of a CANDU 600 MW Nuclear Generating<br />
Stati<strong>on</strong> was limited to meeting the operati<strong>on</strong>al requirements for the initial 25 to 30 years of stati<strong>on</strong> life. However, as of<br />
April 2009, the Wols<strong>on</strong>g-1 stati<strong>on</strong> in South Korea was shut down for a Plant Life Extensi<strong>on</strong> project, which included<br />
retubing of the reactor core. <str<strong>on</strong>g>The</str<strong>on</strong>g> retube work generated large volumes of low and intermediate radioactive retubing waste<br />
streams with specific characteristics that typically cannot be handled and stored within the existing capacity of the Waste<br />
Storage Facility at Wols<strong>on</strong>g site.<br />
Atomic Energy of Canada Limited has identified and assessed the requirements for handling and storing the<br />
radwaste streams generated from retubing a CANDU 600 MW plant. At Wols<strong>on</strong>g-1 CANDU 600 MW Nuclear<br />
Generating Stati<strong>on</strong>, these requirements are met by expanding the existing Waste Storage Facility, design and supply of<br />
retubing waste handling equipment and waste c<strong>on</strong>tainers.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> extensi<strong>on</strong> to the existing Solid Radioactive Waste Management Facility includes c<strong>on</strong>structi<strong>on</strong> of retube waste<br />
canisters. <str<strong>on</strong>g>The</str<strong>on</strong>g>se c<strong>on</strong>crete storage structures are cooled by natural air c<strong>on</strong>vecti<strong>on</strong> and store two types of waste c<strong>on</strong>tainers<br />
for intermediate level waste such as pressure tubes, calandria tubes, calandria tube inserts and end fittings.<br />
Low level waste that is generated by retubing is comprised of: o Reactor comp<strong>on</strong>ents that were exposed to low<br />
neutr<strong>on</strong> flux and c<strong>on</strong>tain activated corrosi<strong>on</strong> product deposits (for example feeder pipe secti<strong>on</strong>s, positi<strong>on</strong>ing assembly<br />
hardware, closure plugs, etc) o Retubing engineered c<strong>on</strong>sumables from tooling that cannot be reused for future retubing<br />
projects, most of which is generated from the following systems: § Retube Active Ventilati<strong>on</strong> System, and § Volume<br />
Reducti<strong>on</strong> System.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> low level waste streams are packaged in Type A boxes for safe transportati<strong>on</strong> of the waste. <str<strong>on</strong>g>The</str<strong>on</strong>g> low level waste<br />
in Type A boxes are stored in the existing Low Level Waste Facility at Wols<strong>on</strong>g site.<br />
This paper describes, at a high level, the following aspects of the design, licensing and commissi<strong>on</strong>ing activities of<br />
the Waste Storage Facility to support retubing of the Wols<strong>on</strong>g-1 CANDU 600 MW Nuclear Generating Stati<strong>on</strong> in South<br />
Korea:<br />
Ø Retubing waste management design requirements; Ø Design of retube waste canisters, waste handling equipment,<br />
waste c<strong>on</strong>tainers for intermediate level waste and Type A boxes for low level waste Ø Licensing process; and Ø<br />
Commissi<strong>on</strong>ing activities.<br />
2) 40284 – Microbial Occurrence in Bent<strong>on</strong>ite-based Buffer Materials of a Final Disposal Site for Low Level<br />
Radioactive Waste in Taiwan<br />
F<strong>on</strong>g-In Chou, Chia-Chin Li, Tzung-Yuang Chen, Nati<strong>on</strong>al Tsing Hua University (Taiwan);<br />
Hsiao-Wei Wen, Nati<strong>on</strong>al Chung Hsing University (Taiwan)<br />
This research addresses the potential of microbial implicati<strong>on</strong>s in bent<strong>on</strong>ite for use as a buffer and backfill material<br />
in final disposal site for low-level radioactive waste (LLRW) in Taiwan, where has a special island-type climate. Microbe<br />
activities naturally present in this site were analyzed, and buffer materials (BM) c<strong>on</strong>sisted of 100%, 70% or 50%<br />
bent<strong>on</strong>ite were prepared for laboratory studies. A total of 39 microbial strains were isolated, and the predominant strains<br />
included four bacterial, <strong>on</strong>e yeast and four fungal strains. Growth inhibiti<strong>on</strong> was not detected in any tested strain cultured<br />
in a radiati<strong>on</strong> field with a dose rate of 0.2 Gy/h. Most of the isolated strains grew under a dose rate of 1.4 Gy/h. <str<strong>on</strong>g>The</str<strong>on</strong>g> D10<br />
values of the tested strains ranged from 0.16 to 2.05 kGy. <str<strong>on</strong>g>The</str<strong>on</strong>g> mycelia of tested fungal strains could spread over 5 cm<br />
during six m<strong>on</strong>ths of inoculati<strong>on</strong> in BM. <str<strong>on</strong>g>The</str<strong>on</strong>g> spreading activity of the tested bacteria was less than that of the fungi.<br />
Moreover, biofilms were observed <strong>on</strong> the surfaces of the BM. Since a large and diverse populati<strong>on</strong> of microbes is present<br />
in Taiwan, microbes may c<strong>on</strong>tribute to the mobilizati<strong>on</strong> of radi<strong>on</strong>uclides in the disposal site.<br />
3) 40153 – Assessing the gas transport mechanisms in the Swiss L/ILW c<strong>on</strong>cept using numerical modeling<br />
Irina Gaus, Paul Marschall, Joerg Rueedi, Nagra (Switzerland);<br />
Rainer Senger, John Ewing, Intera Inc. Swiss Branch (Switzerland)<br />
In low/intermediate-level waste (L/ILW) repositories, anaerobic corrosi<strong>on</strong> of metals and degradati<strong>on</strong> of organic<br />
materials produce hydrogen, methane, and carb<strong>on</strong> dioxide. Gas accumulati<strong>on</strong> and gas transport in a L/ILW repository is<br />
an important comp<strong>on</strong>ent in the safety assessment of proposed deep repositories in low-permeability formati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
dominant gas transport mechanisms are dependent <strong>on</strong> the gas overpressures as with increasing overpressure the gas<br />
transport capacity of the system increases. <str<strong>on</strong>g>The</str<strong>on</strong>g> dominant gas transport mechanisms occurring with increasing gas<br />
pressure within the anticipated pressure ranges are: diffusi<strong>on</strong> of gas dissolved in pore water (1), two phase flow in the<br />
hostrock and the excavati<strong>on</strong> damaged z<strong>on</strong>e (EDZ) whereby no deformati<strong>on</strong> of the pore space occurs (2), gas migrati<strong>on</strong><br />
within parts of the repository (if repository materials are appropriately chosen) (3) and pathway dilati<strong>on</strong> (4). Under no<br />
circumstances the gas is expected to induce permanent fractures in the hostrock. This paper focuses <strong>on</strong> the gas migrati<strong>on</strong><br />
87
Abstracts<br />
in parts of the repository whereby materials are chosen aimed at increasing the gas transport capacity of the backfilled<br />
underground structures without compromising the radi<strong>on</strong>uclide retenti<strong>on</strong> capacity of the engineered barrier system (EBS).<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se materials with enhanced gas permeability and low water permeability can supplement the gas flow that is expected<br />
to occur through the EDZ and the host rock. <str<strong>on</strong>g>The</str<strong>on</strong>g> impact of the use of adapted backfill and sealing materials <strong>on</strong> the gas<br />
pressure build-up and the major gas paths were assessed using numerical two-phase flow models <strong>on</strong> the repository scale.<br />
Furthermore, both the gas and water fluxes as a functi<strong>on</strong> of time and gas generati<strong>on</strong> rate can be evaluated by varying the<br />
physical properties of the materials and hence their transport capacity. Results showed that by introducing seals with<br />
higher gas permeability, the modeled gas flow is largely limited to the access tunnels and the excavati<strong>on</strong> disturbed z<strong>on</strong>e<br />
for the case of a very low permeability host rock. <str<strong>on</strong>g>The</str<strong>on</strong>g> bulk of the gas flows through the repository seal and the adjacent<br />
EDZ into the tunnel system. In additi<strong>on</strong> to the dem<strong>on</strong>strati<strong>on</strong> of the gas flow in the seal and access tunnel system by<br />
numerical models, laboratory results c<strong>on</strong>firm the high gas transport capacity of the sand/bent<strong>on</strong>ite mixtures. In a next step<br />
a multi year dem<strong>on</strong>strati<strong>on</strong> scale experiment (GAST) at the Grimsel Test Site is envisi<strong>on</strong>ed.<br />
4) 40283 – <str<strong>on</strong>g>The</str<strong>on</strong>g> progress and results of Dem<strong>on</strong>strati<strong>on</strong> Test of Cavern-Type Disposal Facility<br />
Yoshihiro Akiyama, Kenji Terada, Nobuaki Oda, Tsutomu Yada, Takahiro Nakajima, RWMC (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity levels mainly<br />
generated from power reactor decommissi<strong>on</strong>ing and for part of transuranic (TRU) waste mainly from spent fuel<br />
reprocessing are designed to be c<strong>on</strong>structed in a cavern 50 to 100 meters below ground, and to employ an engineered<br />
barrier system (EBS) of a combinati<strong>on</strong> of bent<strong>on</strong>ite and cement materials in Japan. In order to advance the feasibility<br />
study for these disposal, a government-commissi<strong>on</strong>ed research project named Dem<strong>on</strong>strati<strong>on</strong> Test of Cavern-Type<br />
Disposal Facility started in fiscal 2005, and since fiscal 2007 a full-scale mock-up test facility has been c<strong>on</strong>structed under<br />
actual subsurface envir<strong>on</strong>ment. <str<strong>on</strong>g>The</str<strong>on</strong>g> main objective of the test is to establish c<strong>on</strong>structi<strong>on</strong> methodology and procedures<br />
which ensure the required quality of the EBS <strong>on</strong>-site. By fiscal 2009 some parts of the facility have been c<strong>on</strong>structed, and<br />
the test has dem<strong>on</strong>strated both practicability of the c<strong>on</strong>structi<strong>on</strong> and achievement of the quality. <str<strong>on</strong>g>The</str<strong>on</strong>g>y are respectively<br />
taken as low-permeability of less than 5x10-13 m/s and low-diffusivity of less than 1x10-12 m2/s at the time of<br />
completi<strong>on</strong> of c<strong>on</strong>structi<strong>on</strong>. This paper covers the project outline and the test results obtained by the c<strong>on</strong>structi<strong>on</strong> of some<br />
parts of a bent<strong>on</strong>ite and cement materials.<br />
SESSION H9: Repository Engineering and Dem<strong>on</strong>strati<strong>on</strong><br />
1) 40304 Keynote – Repository engineering and dem<strong>on</strong>strati<strong>on</strong>: special challenges for TRU<br />
Ian G. McKinley, McKinley C<strong>on</strong>sulting (Switzerland)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> diverse range of l<strong>on</strong>g-lived radioactive wastes without significant heat output specified for deep geological<br />
disposal (here termed TRU) pose challenges that are potentially more serious than those from vitrified high-level waste<br />
and spent fuel. Despite this, the latter tend to be the focus of R&D in nati<strong>on</strong>al programmes. Such challenges are<br />
particularly severe for the case for countries that are not c<strong>on</strong>sidering evaporite host rocks or have a volunteering approach<br />
to siting and those with inventories of TRU resulting from reprocessing of spent fuel. While there is little doubt that safe<br />
disposal of TRU is feasible, it is tricky to develop a c<strong>on</strong>vincing safety case for a site during early stages of<br />
characterisati<strong>on</strong> as, compared to HLW/SF, less credit can be taken for robust, l<strong>on</strong>g-term performance of current designs<br />
of the engineered barrier systems. In order to improve this situati<strong>on</strong> and increase flexibility with respect to host rock<br />
properties, two different opti<strong>on</strong>s are available – improving the c<strong>on</strong>diti<strong>on</strong>ing of particular waste streams or improving the<br />
overall repository safety c<strong>on</strong>cept. Although the former has been a focus for work in some countries (particularly Japan),<br />
much less effort has been invested in the latter and hence this will be illustrated by some examples. In the paper these<br />
opti<strong>on</strong>s will be compared in terms of their pros and c<strong>on</strong>s with respect to practicality of implementati<strong>on</strong>, envir<strong>on</strong>mental<br />
impact and cost. Additi<strong>on</strong>ally, the ease with which the resulting safety case can be supported by dem<strong>on</strong>strati<strong>on</strong>s of key<br />
arguments will be discussed, which may indicate the likely degree of acceptance by stakeholders.<br />
2) 40119 – Half-Scale Test: An important step to dem<strong>on</strong>strate the feasibility of the Belgian Superc<strong>on</strong>tainer<br />
c<strong>on</strong>cept for disposal of HLW<br />
Lou Areias, SCK CEN and VUB (Belgium);<br />
Bart Craeye, Ghent University/Artesis Hogeschool Antwerpen (Belgium);<br />
Geert De Schutter, Ghent University (Belgium);<br />
Hughes Van Humbeeck, William Wacquier, ONDRAF/NIRAS (Belgium);<br />
Alain Van Cotthem, Loic Villers Technum-Tractebel (Belgium)<br />
This paper presents results of a half scale test performed by ESV EURIDICE, an Ec<strong>on</strong>omic Interest Grouping<br />
between the Belgian Nuclear Research Centre (SCK•CEN) and the Belgian Agency for Radioactive Waste and Enriched<br />
Fissile Materials (ONDRAF/NIRAS). <str<strong>on</strong>g>The</str<strong>on</strong>g> primary objective of the test was to assess the feasibility of c<strong>on</strong>structing the<br />
88
Abstracts<br />
Superc<strong>on</strong>tainer and to provide experimental data to validate modelling calculati<strong>on</strong>s obtained using the finite element<br />
program HEAT/MLS. <str<strong>on</strong>g>The</str<strong>on</strong>g> test focused <strong>on</strong> the early age behaviour of the c<strong>on</strong>crete matrix materials and the practical<br />
aspects of c<strong>on</strong>structi<strong>on</strong>. Generally, the results obtained from the half scale test c<strong>on</strong>firm that it is feasible to c<strong>on</strong>struct the<br />
Superc<strong>on</strong>tainer with currently available techniques. <str<strong>on</strong>g>The</str<strong>on</strong>g> results also validate scoping calculati<strong>on</strong>s obtained earlier with<br />
the finite element model. <str<strong>on</strong>g>The</str<strong>on</strong>g>se findings c<strong>on</strong>tribute an important step to dem<strong>on</strong>strate the feasibility to c<strong>on</strong>struct the<br />
Superc<strong>on</strong>tainer and to validate the Belgian Superc<strong>on</strong>tainer c<strong>on</strong>cept proposed by ONDRAF/NIRAS for disposal of high<br />
level waste (HLW) in Belgium.<br />
Keywords: Belgian superc<strong>on</strong>tainer c<strong>on</strong>cept, high-level radioactive waste, half-scale test, c<strong>on</strong>crete buffer, overpack,<br />
c<strong>on</strong>structi<strong>on</strong> feasibility<br />
3) 40175 – Full-Scale Test <strong>on</strong> Overpack Closure Techniques for HLW Repository Operati<strong>on</strong> - Welding Methods<br />
and UT Systems For L<strong>on</strong>g-Term Structural Integrity of the Weld Joint -<br />
Ario Nakamura, Hidekazu Asano, RWMC (Japan);<br />
Takashi Furukawa, JAPAN POWER ENGINEERING AND INSPECTION CORPORATION (Japan);<br />
Kyosuke Fujisawa, KOBE STEEL, LTD. (Japan); Susumu Kawakami, IHI Corporati<strong>on</strong> (Japan);<br />
Takashi Ito, Mitsubishi Heavy Industries, Ltd. (Japan).<br />
Overpack, a high-level radioactive waste package for Japan’s geological disposal program, is required for preventing sealed<br />
vitrified waste from c<strong>on</strong>tact with groundwater for at least 1,000 years. <str<strong>on</strong>g>The</str<strong>on</strong>g> weld joint between the body and lid must also meet this<br />
requirement. Certain welding methods were examined for applicability through full-scale welding tests using various welding depths<br />
up to 190 mm and two different lid structures. Results show that generati<strong>on</strong> of welding flaws must be c<strong>on</strong>sidered unavoidable.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>refore, ultras<strong>on</strong>ic testing (UT) must be c<strong>on</strong>ducted <strong>on</strong> the assumpti<strong>on</strong> that weld flaws will be present. Such UT systems must be<br />
designed for natural defects. Several types of UT must be evaluated for detecti<strong>on</strong> and size estimati<strong>on</strong> capability at depths ranging from<br />
the surface to the bottom of the weld joint. Certain UT methods were examined for their ability to detect natural defects that were<br />
created <strong>on</strong> the surface of and inside a 190-mm thick carb<strong>on</strong> steel specimen. Probability of detecti<strong>on</strong> (POD) of each UT method was<br />
calculated by comparing the results of UT and destructive examinati<strong>on</strong>. In c<strong>on</strong>siderati<strong>on</strong> of the preferred range of scanning depth for<br />
each UT method, a c<strong>on</strong>cept that combines UT methods was proposed as a practical UT system for the overpack weld joint.<br />
KEYWORDS: radioactive waste management, geological disposal, waste package, overpack, final closure weld, structural<br />
integrity, natural defects, UT, POD<br />
4) 40242 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong> Technology, (I) Dem<strong>on</strong>strati<strong>on</strong> and Evaluati<strong>on</strong> of<br />
Remote Handling Technologies<br />
Hitoshi Nakashima, Hidekazu Asano, RWMC (Japan); Hideki Kawamura, Obayashi Corporati<strong>on</strong> (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> l<strong>on</strong>g-term safety of a geological repository for high-level radioactive waste(HLW) in Japan is achieved using a<br />
multi-barrier system, with emphasis <strong>on</strong> an engineered barrier system (EBS) c<strong>on</strong>sisting of bent<strong>on</strong>ite-based buffer material<br />
and a steel overpack c<strong>on</strong>taining vitrified wastes. Providing a wide variety of technical opti<strong>on</strong>s for repository operati<strong>on</strong>,<br />
which can allow EBS c<strong>on</strong>structi<strong>on</strong> under various repository c<strong>on</strong>diti<strong>on</strong>s, is valuable for the volunteering approach to siting<br />
a HLW repository in Japan. In order to c<strong>on</strong>firm technological applicability of candidate techniques and to evaluate<br />
compatibility in an operati<strong>on</strong> system, full-scale tests of various remote-handling and-emplacement techniques for the<br />
EBS were c<strong>on</strong>ducted. <str<strong>on</strong>g>The</str<strong>on</strong>g> test results are summarized in the technical menu which is hierarchical structured database.<br />
Since the l<strong>on</strong>g-term performance of EBS is significantly influenced by remote handling and emplacement techniques for<br />
EBS, c<strong>on</strong>sistency of the operati<strong>on</strong> technology must be evaluated from the view point of system standing. In this program,<br />
evaluati<strong>on</strong> methodology was studied and several indexes, representing requirements for the repository operati<strong>on</strong> and<br />
management, were identified. Indices include current technical availability, l<strong>on</strong>g-term safety of the resultant EBS,<br />
operati<strong>on</strong>al safety, engineering reliability, retrievability, etc., with expert assessment complementing a more quantitative<br />
evaluati<strong>on</strong>.<br />
5) 40251 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong> Technology, (II) Bent<strong>on</strong>ite Block Forming and<br />
Vertical Emplacement/JGC<br />
Hajime Takao, Tatsuhiro Takegahara, JGC Corporati<strong>on</strong> (Japan);<br />
Hitoshi Nakashima, Hidekazu Asano, RWMC (Japan)<br />
RWMC and JGC have been running an all-round R&D program for the period of 2000-2010 to develop the c<strong>on</strong>cept<br />
of Vertical Emplacement for disposal of vitrified waste. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>ceptual design of its basic equipment was worked out in<br />
2000, followed by forming the large-scale bent<strong>on</strong>ite block in 2001-2004. Study has also been c<strong>on</strong>ducted <strong>on</strong> a mechanism<br />
to c<strong>on</strong>vey and positi<strong>on</strong> the large-scale block using a vacuum sucti<strong>on</strong> device. Subsequent to these developments, various<br />
technologies necessary for designing the Vertical Emplacement equipment have been reviewed, which would enhance<br />
engineering feasibility and reliability.<br />
Full-scale dem<strong>on</strong>strati<strong>on</strong> program under a joint research program with JAEA (Japan Atomic Energy Agency)<br />
started in 2008 with the twin objectives i) supporting of public relati<strong>on</strong>s and ii) technical verificati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> large-scale<br />
bent<strong>on</strong>ite block and part of the full-scale Vertical Emplacement equipment are now <strong>on</strong> view at the Full-scale<br />
89
dem<strong>on</strong>strati<strong>on</strong> facility in Hor<strong>on</strong>obe, Hokkaido, Japan.<br />
Abstracts<br />
6) 40268 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong> Technology, (III) Transportati<strong>on</strong> and Horiz<strong>on</strong>tal<br />
Emplacement of Pre-Fabricated EBS Module (PEM)<br />
Susumu Kawakami, IHI Corporati<strong>on</strong> (Japan); Hitoshi Nakashima, Hidekazu Asano, RWMC (Japan)<br />
As <strong>on</strong>e of the repository operati<strong>on</strong> technologies for high-level radioactive waste?(HLW), the pre-fabricated<br />
engineered barrier system (EBS) module (PEM) was carried out the examinati<strong>on</strong> of handling and emplacement technique<br />
for EBS. <str<strong>on</strong>g>The</str<strong>on</strong>g> PEM technology was examined to c<strong>on</strong>firm technological applicability. <str<strong>on</strong>g>The</str<strong>on</strong>g> PEM is c<strong>on</strong>cept of the<br />
integrati<strong>on</strong> of EBS as the module in the surface facilities, and transporting the module underground facilities. This<br />
c<strong>on</strong>cept is the <strong>on</strong>e of the candidate c<strong>on</strong>cepts of horiz<strong>on</strong>tal emplacement techniques for EBS in Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, PEM is<br />
the same level large size and heavy weight as EBS, and it is necessary to examine the applicability of handling and<br />
emplacement techniques. Full-scale level tests were performed to c<strong>on</strong>firm the applicability of these techniques with the<br />
air bearing/air jack devices. In the tests, we prepared the testing devices of full-scale level size/weight and c<strong>on</strong>firmed the<br />
applicability of these technologies as an elemental technology <strong>on</strong> the c<strong>on</strong>diti<strong>on</strong> of c<strong>on</strong>sidering the envir<strong>on</strong>ment of an<br />
underground tunnel. <str<strong>on</strong>g>The</str<strong>on</strong>g> air bearing test that produced the surface-roughness of the tunnel envir<strong>on</strong>ment was carried out<br />
the evaluati<strong>on</strong> c<strong>on</strong>cerning the transportati<strong>on</strong> performance of the air bearing. And, the air jack test was carried out the<br />
holding and emplacement of PEM. <str<strong>on</strong>g>The</str<strong>on</strong>g> repository operati<strong>on</strong> technology with the air bearing/jack device was c<strong>on</strong>firmed<br />
to execute the examinati<strong>on</strong>, and to apply to handling and emplacement technique for PEM.<br />
7) 40236 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong> Technology, (IV) Shotclay Technique for Seamless<br />
C<strong>on</strong>structi<strong>on</strong> of EBS<br />
Ichizo Kobayashi, Soh Fujisawa, Makoto Nakajima, Masaru Toida, Kajima Corporati<strong>on</strong> (Japan);<br />
Hitoshi Nakashima, Hidekazu Asano, RWMC (Japan)<br />
In Japan, the c<strong>on</strong>structi<strong>on</strong> method of the buffer material has been investigated focusing <strong>on</strong> the block emplacement<br />
and in-situ compacti<strong>on</strong> methods. Under the current c<strong>on</strong>cept of geological disposal of radioactive waste, since it has been<br />
important that the barrier satisfies the dry density requirement as a mass, no enough attenti<strong>on</strong> has been paid to the<br />
distributi<strong>on</strong> of density and the gaps between blocks which were caused by the c<strong>on</strong>venti<strong>on</strong>al methods. This is based <strong>on</strong> the<br />
assumpti<strong>on</strong> that bent<strong>on</strong>ite swells from the permeati<strong>on</strong> of groundwater and that the density eventually becomes<br />
homogeneous. However, it is not clear whether the high density bent<strong>on</strong>ite does in fact swell until the density is<br />
homogeneous. <str<strong>on</strong>g>The</str<strong>on</strong>g> effects of density distributi<strong>on</strong> and the gaps in l<strong>on</strong>g-term high impermeability of a<br />
bent<strong>on</strong>ite-engineered barrier may be not small. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, the opti<strong>on</strong> of the c<strong>on</strong>structi<strong>on</strong> method for a<br />
bent<strong>on</strong>ite-engineered barrier that does not have such uncertainty c<strong>on</strong>cerning the implementati<strong>on</strong> of a disposal c<strong>on</strong>cept<br />
should be prepared. In order to remove such uncertainty, the high-density spray method for bent<strong>on</strong>ite, termed the<br />
shotclay method, was developed as a method for c<strong>on</strong>structing a uniform bent<strong>on</strong>ite-engineered barrier without gaps even<br />
in a narrow space. <str<strong>on</strong>g>The</str<strong>on</strong>g> shotclay method is used to c<strong>on</strong>struct compacted soil at high density by spraying material<br />
prec<strong>on</strong>diti<strong>on</strong>ed with water. Using this method, the dry density of 1.6 Mg /m3, which was c<strong>on</strong>sidered impossible with the<br />
spraying method, is achieved. In this study, the applicability of the shotclay method to HLW bent<strong>on</strong>ite-engineered<br />
barriers was c<strong>on</strong>firmed experimentally. In the tests, an actual scale vertical-type HLW bent<strong>on</strong>ite engineered barrier was<br />
c<strong>on</strong>structed. This was a bent<strong>on</strong>ite-engineered barrier with a diameter of 2.22 m and a height of 3.13 m. <str<strong>on</strong>g>The</str<strong>on</strong>g> material used<br />
was bent<strong>on</strong>ite with 30% silica sand, and water c<strong>on</strong>tent was adjusted by mixing chilled bent<strong>on</strong>ite with powdered ice<br />
before thawing. Work progress was 11.2 m3 and the weight was 21.7 Mg. <str<strong>on</strong>g>The</str<strong>on</strong>g> dry density of the entire buffer was 1.62<br />
Mg/m3, and c<strong>on</strong>structi<strong>on</strong> time was approximately 8 hours per unit. After the formworks were removed, the core and<br />
block of the actual scale HLW bent<strong>on</strong>ite-engineered barrier were sampled to c<strong>on</strong>firm homogeneity. As a result,<br />
homogeneity was c<strong>on</strong>firmed, and no gaps were observed between the formwork and the buffer material and between the<br />
simulated waste and the buffer material. <str<strong>on</strong>g>The</str<strong>on</strong>g> applicability to HLW of the shotclay method has been c<strong>on</strong>firmed through<br />
this examinati<strong>on</strong>.<br />
8) 40254 – Design Opti<strong>on</strong>s for HLW Repository Operati<strong>on</strong> Technology, (V) Preliminary Study and Small Scale<br />
Experiments <strong>on</strong> the Method of Removal of Buffer Material with Salt Soluti<strong>on</strong><br />
Satohito Toguri, Jiho Jang, Takashi Ishii, Mitsunobu Okihara, Kengo Iwasa, SHIMIZU CORPORATION (Japan);<br />
Hitoshi Nakashima, Hidekazu Asano, RWMC (Japan)<br />
During the c<strong>on</strong>structi<strong>on</strong> of geological disposal facilities for high-level radioactive waste, it may be decided to free<br />
and retrieve the emplaced overpack for some reas<strong>on</strong>s. Thus we have been paying attenti<strong>on</strong> to a method of slurrying<br />
bent<strong>on</strong>ite buffer around the overpack with fluid (salt soluti<strong>on</strong>) for freeing it. A few laboratory tests were performed to<br />
research the feasibility and verify the applicability of the method. <str<strong>on</strong>g>The</str<strong>on</strong>g> test piece of the buffer material c<strong>on</strong>sists of 70wt%<br />
bent<strong>on</strong>ite and 30wt% sand, and its dry density is 1.6 g/mL, and the volume of the cylindrical test piece is 100mL. First,<br />
the time was measured for test pieces to be dissolved in various strength NaCl soluti<strong>on</strong>s. In case of 47% saturated test<br />
pieces, they could be easily dissolved in NaCl 3 or 4wt% soluti<strong>on</strong>, and the dissolved material was deposited so<strong>on</strong> in the<br />
slurry. Sec<strong>on</strong>d, the results from the flushing experiments applied to a small specimen of buffer material suggest that<br />
flushing 4wt% NaCl soluti<strong>on</strong> is effective for speedy stripping of buffer material. Third, the times were measured for<br />
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Abstracts<br />
various percentage saturated test pieces to be dissolved in 4wt% NaCl soluti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> time for 47% saturated <strong>on</strong>e was<br />
shorter than 1 Hr, but the time for 67% was l<strong>on</strong>ger than 5 Hrs. In case of 88%, it had not been dissolved yet in 7Hrs, but<br />
after drying the test piece it could be easily dissolved in 5 minutes. <str<strong>on</strong>g>The</str<strong>on</strong>g> results from the laboratory tests indicate that the<br />
unsaturated buffer material can be easily dissolved in NaCl 4wt% soluti<strong>on</strong>, and the wet buffer material can be dissolved<br />
by immersing in NaCl 4wt% soluti<strong>on</strong> after process of dry-hot-air blowing. Finally, in order to c<strong>on</strong>firm the effect of<br />
removal processes, simulated experiments were executed using small scale (1/14 scale) specimens. <str<strong>on</strong>g>The</str<strong>on</strong>g> 47% saturated<br />
buffer material specimen was easily removed by the process of immersing in NaCl soluti<strong>on</strong>, flushing NaCl soluti<strong>on</strong>,<br />
removing slurry by vacuum device, and re-using NaCl soluti<strong>on</strong> after depositi<strong>on</strong>. In the nearly saturated case, it was<br />
removed in cyclic process of dry-hot-air blowing and immersing in NaCl 4wt% soluti<strong>on</strong>.<br />
SESSION H10: Site Characterizati<strong>on</strong> and Modeling of Geological Envir<strong>on</strong>ment (2)<br />
1) 40135 – Dry-run of Site Investigati<strong>on</strong> Planning using the Manual for Preliminary Investigati<strong>on</strong> in Japan<br />
Shigeki Akamura, Tadashi Miwa, NUMO (Japan); Tatsuya Tanaka, Obayashi Corporati<strong>on</strong> (Japan);<br />
Hiroshi Shiratsuchi, Tokyo Electric Power Service Co.,Ltd. (Japan);<br />
Atsushi Horio, DIA CONSULTANTS CO., Ltd. (Japan)<br />
A stepwise site selecti<strong>on</strong> process has been adopted for geological disposal of HLW in Japan. Literature surveys,<br />
followed by preliminary investigati<strong>on</strong>s (PI) and, finally, detailed investigati<strong>on</strong>s in underground facilities will be carried<br />
out in the successive selecti<strong>on</strong> stages. In the PI stage, surface-based investigati<strong>on</strong>s such as borehole surveys and<br />
geophysical prospecting will be implemented.<br />
NUMO recognizes that sustained improvement of internal expertise is very important to ensure that the PI will be<br />
implemented rigorously and efficiently. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore existing knowledge and experience in the planning and management<br />
of site investigati<strong>on</strong>s were compiled in the form of two manuals: the Preliminary Investigati<strong>on</strong> Planning Manual (PIPM)<br />
and the Preliminary Investigati<strong>on</strong> Management Manual (PIMM). <str<strong>on</strong>g>The</str<strong>on</strong>g> manuals were based <strong>on</strong> the experience in overseas<br />
site investigati<strong>on</strong> programs, and has further been refined by taking experience from site investigati<strong>on</strong>s in Japan (e.g. from<br />
generic URLs) into account. NUMO has applied them in its own R&D programs, such as the dry-run studies for various<br />
geological envir<strong>on</strong>ments (e.g. coastal and island).<br />
This paper outlines the process and the results of a dry-run study which applied the revised PIPM to the Yokosuka<br />
area where the dem<strong>on</strong>strati<strong>on</strong> and validati<strong>on</strong> project for PI technologies has been c<strong>on</strong>ducted. <str<strong>on</strong>g>The</str<strong>on</strong>g> planning of the PI was<br />
performed according to the eight steps in the PIPM. <str<strong>on</strong>g>The</str<strong>on</strong>g> GET (Geosphere Evaluati<strong>on</strong> Team) c<strong>on</strong>sisting of staffs from site<br />
characterizati<strong>on</strong>, performance assessment and repository design groups in NUMO, was established for the PI planning.<br />
This task force team has resp<strong>on</strong>sibility not <strong>on</strong>ly for the planning but also for making key decisi<strong>on</strong>s regarding the<br />
performance of the program. <str<strong>on</strong>g>The</str<strong>on</strong>g> SDMT (Site Descriptive Modeling Team) was formed for site modeling activities.<br />
Initial geoscientific c<strong>on</strong>ceptual models were established based <strong>on</strong> the interpretati<strong>on</strong> of existing site informati<strong>on</strong> around<br />
the area. Various c<strong>on</strong>ceptual models were c<strong>on</strong>structed due to the limited amount of existing informati<strong>on</strong>. Site descriptive<br />
models were derived taking such variati<strong>on</strong>s in the c<strong>on</strong>ceptual models into account. <str<strong>on</strong>g>The</str<strong>on</strong>g> main targets for the PI planning<br />
were specified c<strong>on</strong>sidering the uncertainties in the models, requests from the repository c<strong>on</strong>cept as well as legal<br />
requirement. <str<strong>on</strong>g>The</str<strong>on</strong>g> integrated PI program set out the sequence of investigati<strong>on</strong>s and characterizati<strong>on</strong> activities to achieve<br />
the main targets. Less<strong>on</strong>s learned in the PI planning and the applicability of the revised PIPM were addressed as the<br />
c<strong>on</strong>clusi<strong>on</strong> of the dry-run.<br />
2) 40070 – Evaluati<strong>on</strong> of the l<strong>on</strong>g-term evoluti<strong>on</strong> of the groundwater system in the Mizunami area, Japan<br />
Takashi Mizuno, Teruki Iwatsuki, JAEA (Japan); Ant<strong>on</strong>i E. Milodowski, British Geological Survey (UK)<br />
This study aimed to develop a methodology for assessing the evoluti<strong>on</strong> of the l<strong>on</strong>g-term groundwater system, using<br />
fracture-filling calcite. Fracture-filling calcite mineralizati<strong>on</strong>, closely associated with groundwater flow paths, in deep (to<br />
ca. 1000 m) granitic rocks in and around Mizunami area, Japan, was studied by optical and cathode-luminescence<br />
microscopy, SEM, laser ablati<strong>on</strong> microprobe-ICP MS, stable isotope geochemistry, and fluid inclusi<strong>on</strong> analysis. As the<br />
results, four generati<strong>on</strong>s (I to IV) of calcite precipitati<strong>on</strong> can be differentiated based <strong>on</strong> their morphological and isotopic<br />
characteristics. Calcite I - calcite with indistinct morphology including the wall rock fragments (d13CPDB -31.4 ‰ ~<br />
-7.5 ‰, d18OPDB -32.7 ‰ ~ -8.0 ‰); Calcite II -calcite with euhedral rhombohedral and hexag<strong>on</strong>al crystal forms<br />
(d13CPDB 22.5 ‰ ~ -1.8 ‰, d18OPDB -15.5 ‰ ~ -6.5 ‰); Calcite III - calcite forming c-axis el<strong>on</strong>gated rhombohedral<br />
overgrowths seeded <strong>on</strong> top of Calcite II (d13CPDB -18.0 ‰ ~ 5.8 ‰, d18OPDB -11.1 ‰ ~ -2.3 ‰); Calcite IV - calcite<br />
forming small rhombohedral crystals nucleated <strong>on</strong> the surface of Calcite III (d13CPDB -12.5 ‰ ~ -1.7 ‰, d18OPDB<br />
-12.7 ‰~7.8 ‰). Carb<strong>on</strong> and oxygen isotopic ratios suggests that the Calcite I is of hydrothermal origin. On the other<br />
hand, Calcite II, IV and III were precipitated from freshwater and marine water, respectively. From the geohistorical<br />
point of view, depositi<strong>on</strong>al setting in Mizunami area was changed during Tertiary and Quaternary. Mizunami Group<br />
overlying above Toki granite is changed from lacustrine strata to marine strata. In additi<strong>on</strong>, upper Seto Group is a<br />
lacustrine stratum. <str<strong>on</strong>g>The</str<strong>on</strong>g> change of depositi<strong>on</strong>al setting corresp<strong>on</strong>ds to groundwater system assumed by mineralogical<br />
study. As there is no other evidence linked to penetrati<strong>on</strong> of high-salinity water into deep envir<strong>on</strong>ment in this area, it is<br />
91
Abstracts<br />
suggested that both of depositi<strong>on</strong> of marine strata (upper part of Mizunami group) and forming Calcite III precipitati<strong>on</strong><br />
were possibly caused by same transgressi<strong>on</strong> event. After Calcite III precipitati<strong>on</strong>, calcite IV was precipitated from fresh<br />
water during flushing of the marine water. As summary, integrated morphological, mineralogical, microchemical and<br />
isotopic analysis of multilayered calcite fracture mineralizati<strong>on</strong> associated with groundwater flow paths provides valuable<br />
informati<strong>on</strong> to evaluate l<strong>on</strong>g-term evoluti<strong>on</strong> of groundwater system.<br />
3) 40077 – Study <strong>on</strong> the Estimati<strong>on</strong> Error Caused by Using One-dimensi<strong>on</strong>al Model for the Evaluati<strong>on</strong> of Dipole<br />
Tracer Test<br />
Yuji Ijiri, Yumi Naemura, Taisei Corporati<strong>on</strong> (Japan);<br />
Kenji Amano, Keisuke Maekawa, Kunio Ota, Takanori Kunimaru, Atsushi Sawada, JAEA (Japan)<br />
In-situ tracer tests are of value in obtaining parameters for repository performance assessment. A <strong>on</strong>e-dimensi<strong>on</strong>al<br />
model is simple and has thus been comm<strong>on</strong>ly employed to identify the radi<strong>on</strong>uclide transport parameters by fitting the<br />
model to breakthrough curves obtained from the tracer tests. It can, however, be c<strong>on</strong>sidered that the <strong>on</strong>e-dimensi<strong>on</strong>al<br />
model could increase uncertainty in the identified parameters. In particular, such errors are not negligible when the<br />
parameters are evaluated for the test c<strong>on</strong>ducted in a dipole (twodimensi<strong>on</strong>al) flow field between injecti<strong>on</strong> and pumping<br />
wells. In this study, the effects of various experimental c<strong>on</strong>diti<strong>on</strong>s including pumping rate, dipole ratio, heterogeneity of<br />
fracture transmissivity and background groundwater flow <strong>on</strong> the identified parameters are investigated using computer<br />
simulati<strong>on</strong>s for the case of tracer tests in a fracture plane. L<strong>on</strong>gitudinal dispersivity tends to be overestimated by using<br />
the <strong>on</strong>e-dimensi<strong>on</strong>al model and to become larger when the pumping rate becomes smaller, the dipole ratio larger, the<br />
heterogeneity of the fracture str<strong>on</strong>ger and orthog<strong>on</strong>al oriented background groundwater flow greater. Such informati<strong>on</strong><br />
will be of much help for planning tracer tests in an appropriate manner at underground research laboratories both at<br />
Mizunami in central Japan and Hor<strong>on</strong>obe in northern Japan. Definiti<strong>on</strong> of appropriate experimental c<strong>on</strong>diti<strong>on</strong>s will<br />
c<strong>on</strong>tribute to decreasing the uncertainty in the results of the tracer tests.<br />
4) 40056 – Development of Comprehensive Techniques for Coastal Site Characterisati<strong>on</strong> (1) Strategic Overview<br />
Kunio Ota, Kenji Amano, Tadafumi Niizato, JAEA (Japan);<br />
W Russell Alexander, Bedrock Geosciences (Switzerland);<br />
Yoshiaki Yamanaka, Suncoh C<strong>on</strong>sultants (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> assurance of the l<strong>on</strong>g-term stability of the geological envir<strong>on</strong>ment is sine qua n<strong>on</strong> for deep geological disposal.<br />
Any assessment of repository safety will thus require development of a set of analyses and arguments to dem<strong>on</strong>strate the<br />
persistence of the key safety functi<strong>on</strong>s of the geological envir<strong>on</strong>ment up to several hundred thousand years into the future,<br />
taking into account the likely future evoluti<strong>on</strong> of the repository host rock.<br />
C<strong>on</strong>cern presently focusses <strong>on</strong> a sea-level rise caused by anthropogenic global warming but, within a period of<br />
several tens of thousands of years, a return to glacial-period c<strong>on</strong>diti<strong>on</strong>s is to be expected. Based <strong>on</strong> previous glaciati<strong>on</strong>s,<br />
global sea-level could drop by up to 150 m and, in the case of Japan, such a decrease in sea-level would result in an<br />
extremely dramatic change in the locati<strong>on</strong> of coastal lines with a subsequent significant change to hydraulic and<br />
hydrochemical c<strong>on</strong>diti<strong>on</strong>s at coastal sites. It is thus of great importance in the Japanese disposal programme to establish<br />
comprehensive techniques for characterising the overall evoluti<strong>on</strong> of coastal sites over geological time with focus very<br />
much <strong>on</strong> the persistence of the key safety functi<strong>on</strong>s throughout episodes of uplift/subsidence and climatic and sea-level<br />
changes.<br />
To this end, based <strong>on</strong> practical experience from the <strong>on</strong>going underground research laboratory projects of JAEA, a<br />
transparent and traceable roadmap for planning and implementing a sequence of field investigati<strong>on</strong>s at any coastal site<br />
has been formulated. Known as a “Geosynthesis Data Flow Diagram (GDFD)”, this system illustrates linkages between a<br />
range of parameters, including investigati<strong>on</strong>s of key aspects to be addressed, interpretati<strong>on</strong> of data acquired, synthesis of<br />
the results of different studies and analyses and final clarificati<strong>on</strong> of the key properties and processes of the geological<br />
envir<strong>on</strong>ment. In particular, the GDFD defines a geosynthesis methodology for describing temporal and spatial changes of<br />
various characteristics and processes, with particular focus <strong>on</strong> the site palaeohydrogeology.<br />
Such a geosynthesis methodology has been introduced in an <strong>on</strong>going collaborative programme for characterising<br />
the coastal geological envir<strong>on</strong>ment around Hor<strong>on</strong>obe in northern Hokkaido, Japan. A basic strategy for stepwise<br />
investigati<strong>on</strong>s has been proposed, which incorporates the geosynthesis methodology in an effective manner in each step<br />
from initial survey/review of existing informati<strong>on</strong>, through aerial, terrestrial and marine explorati<strong>on</strong>, to the final borehole<br />
programme. This technique has now been tested and optimised based <strong>on</strong> technical findings and experience that have been<br />
accumulated with the progress of the investigati<strong>on</strong>s.<br />
5) 40052 – Development of comprehensive techniques for coastal site characterisati<strong>on</strong>: (3) C<strong>on</strong>ceptualisati<strong>on</strong> of<br />
l<strong>on</strong>g-term geosphere evoluti<strong>on</strong><br />
Tadafumi Niizato, Kenji Amano, Kunio Ota, Takanori Kunimaru, JAEA (Japan);<br />
Lany<strong>on</strong> Bill, Nagra (Switzerland);<br />
W Russell Alexander, Bedrock Geosciences (Switzerland)<br />
92
Abstracts<br />
A critical issue for building c<strong>on</strong>fidence in the l<strong>on</strong>g-term safety of geological disposal is to dem<strong>on</strong>strate the stability<br />
of the geosphere, taking into account its likely future evoluti<strong>on</strong>. This stability is broadly defined as the persistence of<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>rmal-Hydrological-Mechanical-Chemical c<strong>on</strong>diti<strong>on</strong>s c<strong>on</strong>sidered favourable for the l<strong>on</strong>g-term safety of a geological<br />
repository. <str<strong>on</strong>g>The</str<strong>on</strong>g> geosphere is slowly but c<strong>on</strong>stantly evolving, and then the stability, in this case, does not imply that<br />
steady-state c<strong>on</strong>diti<strong>on</strong>s exist. What is important is that the evoluti<strong>on</strong> of the geosphere can be understood. In general, an<br />
understanding of the evoluti<strong>on</strong> is gained by studying the palaeohydrogeological evoluti<strong>on</strong> of a site, defining temporal and<br />
spatial changes of various characteristics, events, and processes over geological time. <str<strong>on</strong>g>The</str<strong>on</strong>g> site palaeohydrogeology refers<br />
to natural events and processes that have occurred in the past and c<strong>on</strong>tributed to the present state of the geosphere, which<br />
include sub-surface processes (e.g. crustal movement, diagenesis, etc.) and earth-surface processes (e.g. climatic and<br />
sea-level changes, geomorphological processes, etc.). An understanding of the palaeohydrogeological evoluti<strong>on</strong> of the<br />
site provides the firm foundati<strong>on</strong> to describe the likely future evoluti<strong>on</strong> of the site. An <strong>on</strong>going collaborative programme<br />
aims to establish comprehensive techniques for characterising the overall evoluti<strong>on</strong> of coastal sites through studying the<br />
palaeohydrogeological evoluti<strong>on</strong> in the coastal system around the Hor<strong>on</strong>obe area, Hokkaido, northern Japan. In this study,<br />
the current status for the c<strong>on</strong>ceptualisati<strong>on</strong> of the l<strong>on</strong>g-term geosphere evoluti<strong>on</strong> in the coastal area, is based <strong>on</strong> data from<br />
the JAEA’s underground research laboratory project. Informati<strong>on</strong> <strong>on</strong> surface and sub-surface processes has been<br />
integrated into a chr<strong>on</strong>ological c<strong>on</strong>ceptual model which indicates space-time sequences of the events and processes in the<br />
area over geological time. Spatial scale for the c<strong>on</strong>ceptualisati<strong>on</strong> is ca. 100 km in the East-West directi<strong>on</strong> through the<br />
locati<strong>on</strong>s of the underground research laboratory and of the borehole investigati<strong>on</strong>s <strong>on</strong> the coast in the Hor<strong>on</strong>obe area.<br />
Temporal c<strong>on</strong>ceptualisati<strong>on</strong>s over the last few milli<strong>on</strong> years are focused <strong>on</strong> the spatial and temporal changes of the<br />
geosphere caused by sub-surface processes and over the last several hundred thousand years focused <strong>on</strong> the changes<br />
caused by earth-surface processes. <str<strong>on</strong>g>The</str<strong>on</strong>g> methodology for c<strong>on</strong>ceptualisati<strong>on</strong> of the geosphere evoluti<strong>on</strong> will be applied to<br />
other analogous coastal areas <strong>on</strong> Japan’s western seaboard to produce comprehensive techniques to support<br />
understanding the geosphere evoluti<strong>on</strong> of potential coastal sites for deep geological repositories.<br />
6) 40048 – Development of Comprehensive Techniques for Coastal Site Characterisati<strong>on</strong> (2) Integrated<br />
Palaeohydrogeological Approach for Development of Site Evoluti<strong>on</strong> Models<br />
Kenji Amano, Tadafumi Niizato, Hideharu Yokota, Kunio Ota, JAEA (Japan);<br />
Bill Lany<strong>on</strong>, Nagra (Switzerland);<br />
W Russell Alexander, Bedrock Geosciences (Switzerland)<br />
Radioactive waste repository designs c<strong>on</strong>sist of multiple safety barriers which include the waste form, the canister,<br />
the engineered barriers and the geosphere. In many waste programmes, it is c<strong>on</strong>sidered that the three most important<br />
safety features provided by the geosphere are mechanical stability, favourable geochemical c<strong>on</strong>diti<strong>on</strong>s and low<br />
groundwater flux. To guarantee that a repository site will provide such c<strong>on</strong>diti<strong>on</strong>s for timescales of relevance to the<br />
safety assessment, any repository site characterisati<strong>on</strong> has to not <strong>on</strong>ly define whether these features will functi<strong>on</strong><br />
appropriately today, but also to assess if they will remain adequate up to several thousand to hundreds of thousand years<br />
into the future, depending <strong>on</strong> the repository type.<br />
In general, this is d<strong>on</strong>e by studying the palaeoKHNPgeological evoluti<strong>on</strong> of a site, defining temporal and spatial<br />
changes of various characteristics and processes. <str<strong>on</strong>g>The</str<strong>on</strong>g>se may include hydrogeology, geology, groundwater flow<br />
characteristics, groundwater chemistry and site tect<strong>on</strong>ics, including uplift and erosi<strong>on</strong> processes. <str<strong>on</strong>g>The</str<strong>on</strong>g>se key aspects are<br />
studied to build up a c<strong>on</strong>ceptual model for the overall site evoluti<strong>on</strong> over geological time, up to the present and this is<br />
used to define the likely future evoluti<strong>on</strong> of the site and to assess if the main safety features will c<strong>on</strong>tinue to functi<strong>on</strong><br />
adequately.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> collaborative programme described here is focussed <strong>on</strong> the palaeohydrogeology of the coastal area around<br />
Hor<strong>on</strong>obe in northern Hokkaido, Japan. Data from JAEA’s <strong>on</strong>going underground research laboratory project is being<br />
synthesised in a Site Descriptive Model (SDM) with new informati<strong>on</strong> from the collaborating research institutes to<br />
develop a Site Evoluti<strong>on</strong> Model (SEM), with the focus very much <strong>on</strong> changes in the Sea of Japan seaboard over the last<br />
few milli<strong>on</strong> years. This new c<strong>on</strong>ceptual model will then be used to assess the palaeohydrological evoluti<strong>on</strong> of other<br />
analogous sites <strong>on</strong> Japan’s western seaboard, with the final aim of producing a set of comprehensive techniques to<br />
understand the palaeohydrogeological evoluti<strong>on</strong> of the deep geosphere of all coastal sites <strong>on</strong> the Sea of Japan.<br />
7) 40041 – Development of Methodology of Groundwater Flow and Solute Transport Analysis in the Hor<strong>on</strong>obe<br />
Area, Hokkaido, Japan<br />
Keisuke Maekawa, Hitoshi Makino, Hiroshi Kurikami, Tadafumi Niizato, Manabu Inagaki,<br />
Makoto Kawamura, JAEA (Japan)<br />
It is important for establishment of safety assessment techniques of geological disposal to understand groundwater<br />
flow and solute transport accurately. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, we are positi<strong>on</strong>ing to c<strong>on</strong>firm an applicability of the techniques in<br />
realistic envir<strong>on</strong>ment as a crucial issue in R&D. We have attempted and planed some relevant studies as below: -A<br />
methodology to integrate activities from site investigati<strong>on</strong>s to evaluati<strong>on</strong> of solute transport was examined. We have<br />
carried out groundwater flow analysis <strong>on</strong> a regi<strong>on</strong>al scale using geological and hydrological informati<strong>on</strong> from<br />
surface-based investigati<strong>on</strong>s at the Hor<strong>on</strong>obe area, and also solute transport analysis based <strong>on</strong> the informati<strong>on</strong> of the<br />
trajectory analysis. -We have carried out a preliminary simulati<strong>on</strong> of groundwater flow and salinity c<strong>on</strong>centrati<strong>on</strong><br />
distributi<strong>on</strong> using informati<strong>on</strong> <strong>on</strong> climatic and sea-level changes, and evoluti<strong>on</strong> of geological structures c<strong>on</strong>sidering the<br />
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Abstracts<br />
impacts of natural events and processes. C<strong>on</strong>sequently, we could outline the impacts of natural events and processes <strong>on</strong><br />
geological envir<strong>on</strong>ment including hydrogeology, hydrochemistry and their evoluti<strong>on</strong>s. -We have been planning to<br />
develop and apply a methodology of groundwater flow and solute transport analysis to the shallow part, the Hor<strong>on</strong>obe<br />
coastal area and around the URL. <str<strong>on</strong>g>The</str<strong>on</strong>g>se techniques would become a basis for future site specific safety assessment in<br />
Japan.<br />
SESSION D6: Waste Treatment and N<strong>on</strong>-Reactor<br />
1) 40105 – Estimati<strong>on</strong> of Radioactivity of Graphite Blocks in Tokai Power Stati<strong>on</strong> using Statistical Method<br />
Masaaki Nakano, Fuji Electric Holdings Co., Ltd. (Japan);<br />
Hisashi Mikami, Fuji Electric Systems Co., Ltd. (Japan);<br />
Hideaki Ichige, Shinich Tsukada, JAPC (Japan)<br />
Tokai Power Stati<strong>on</strong> (graphite moderated, gas-cooled reactor, GCR) stopped its commercial operati<strong>on</strong> in March<br />
1998 and is decommissi<strong>on</strong>ing now. Since graphite blocks in Tokai reactor core are major low level wastes (LLWs), the<br />
realistic and reas<strong>on</strong>able method to estimate radioactivity of graphite blocks is required for final disposal and its licensing<br />
procedure. In general, LLWs, which were installed in or around a reactor core, have large radioactivity, theoretical<br />
calculati<strong>on</strong>s can be applied to the estimati<strong>on</strong> of the radioactivity. This paper describes the c<strong>on</strong>cept of the method using<br />
statistical approach to determine the radioactivity of the graphite blocks in the reactor core. This method directly<br />
c<strong>on</strong>siders the variati<strong>on</strong>s of input calculati<strong>on</strong> c<strong>on</strong>diti<strong>on</strong>s, for example, compositi<strong>on</strong>s of impurity elements, irradiati<strong>on</strong><br />
neutr<strong>on</strong> flux and irradiati<strong>on</strong> period. In this paper, the variati<strong>on</strong>s of the compositi<strong>on</strong>s of impurity elements were<br />
statistically c<strong>on</strong>sidered with the mean value and the standard deviati<strong>on</strong> that were determined with elemental analyses.<br />
Many activati<strong>on</strong> calculati<strong>on</strong>s were performed with the compositi<strong>on</strong>s that were determined with pseudorandom numbers,<br />
the mean value and the standard deviati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> calculated radioactivities distribute also statistically and a mean value and<br />
a standard deviati<strong>on</strong> of radioactivity can be determined. <str<strong>on</strong>g>The</str<strong>on</strong>g> distributi<strong>on</strong> of calculated radioactivities shows c<strong>on</strong>sistency<br />
to radiochemical analyses of graphite blocks from the reactor core and this shows that the method is applicable to the<br />
estimati<strong>on</strong> of the graphite block radioactivity. Furthermore, this method can be c<strong>on</strong>sidered to reduce over-excess<br />
estimati<strong>on</strong> margin and can obtain reas<strong>on</strong>able radioactivity rather than using maximum or c<strong>on</strong>servative values of all input<br />
c<strong>on</strong>diti<strong>on</strong>s. This method is now being developed and approved as <strong>on</strong>e of basic procedure for determining the<br />
radioactivity of wastes by Standards Committee of the Atomic Energy Society of Japan.<br />
2) 40115 – <str<strong>on</strong>g>The</str<strong>on</strong>g> treatment of hexavalent chromium in waste liquid from Fugen Decommissi<strong>on</strong>ing<br />
Yuki Yahiro, Seiji Yamamoto, Koji Negishi, Hitoshi Sakai, Tadashi Fukushima,<br />
Norimasa Yoshida, Toshiba Corporati<strong>on</strong> (Japan); Nobuo Ishizuka, Yuji Sato, Wataru Fujiwara, JAEA (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> prototype Advanced <str<strong>on</strong>g>The</str<strong>on</strong>g>rmal Reactor (ATR) Fugen Nuclear Power Stati<strong>on</strong> of JAEA terminated its operati<strong>on</strong> in<br />
2003 and is under decommissi<strong>on</strong>ing. In cooling water (90m3) for ir<strong>on</strong>-water shield c<strong>on</strong>crete surrounding the core regi<strong>on</strong>,<br />
hexavalent chromium (K2CrO4) was dissolved as corrosi<strong>on</strong> inhibitor. <str<strong>on</strong>g>The</str<strong>on</strong>g> hexavalent chromium has to be reduced to<br />
trivalent chromium, for the safety. Authors had developed a new treatment technique for the waste liquid c<strong>on</strong>taining<br />
hexavalent chromium with small amount of sec<strong>on</strong>dary waste. We manufactured and installed test equipment, and we<br />
treated the waste liquid in Fugen. We added formic acid as pH adjuster in the water and hydrogen peroxide to reduce<br />
hexavalent chromium to trivalent chromium. <str<strong>on</strong>g>The</str<strong>on</strong>g> residual hydrogen peroxide was decomposed to oxygen and water with<br />
ir<strong>on</strong> catalysis and UV lamp. <str<strong>on</strong>g>The</str<strong>on</strong>g>n cati<strong>on</strong>ic species, such as trivalent chromium and potassium, in waste liquid were<br />
removed by cati<strong>on</strong> exchange resin. <str<strong>on</strong>g>The</str<strong>on</strong>g> hydrogen peroxide and ir<strong>on</strong> catalysis were added again to decompose the residual<br />
formic acid to carb<strong>on</strong> dioxide gas and water. Next, the residual hydrogen peroxide was decomposed by catalase. Finally,<br />
all the i<strong>on</strong>ic species in the waste liquid were removed by mixed resin. It was c<strong>on</strong>firmed that the c<strong>on</strong>centrati<strong>on</strong> of<br />
hexavalent chromium could be reduced to below 0.5ppm and total chromium c<strong>on</strong>centrati<strong>on</strong> to below 2.0ppm. This value<br />
is below the water polluti<strong>on</strong> preventi<strong>on</strong> law. It took 5 days for the whole treatment of 5m3 waste liquid c<strong>on</strong>taining the<br />
hexavalent chromium 340ppm.<br />
3) 40201 – Characterizati<strong>on</strong> of Radioactive Waste from Side Structural Comp<strong>on</strong>ents of a CANDU Reactor for<br />
Decommissi<strong>on</strong>ing Applicati<strong>on</strong>s in Korea<br />
Rizwan Ahmed, Gyunyoung Heo, Kyung Hee University (Korea Rep.);<br />
D<strong>on</strong>g-Keun Cho, J<strong>on</strong>gw<strong>on</strong> Choi, KAERI (Korea Rep.)<br />
Reactor core comp<strong>on</strong>ents and structural materials of nuclear power plants to be decommissi<strong>on</strong>ed have been<br />
irradiated by neutr<strong>on</strong>s of various intensities and spectrum. This l<strong>on</strong>g term irradiati<strong>on</strong> results in the producti<strong>on</strong> of large<br />
number of radioactive isotopes that serve as a source of radioactivity for thousands of years for future. Decommissi<strong>on</strong>ing<br />
of a nuclear reactor is a costly program comprising of dismantling, demolishing of structures and waste classificati<strong>on</strong> for<br />
disposal applicati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> estimate of radio-nuclides and radiati<strong>on</strong> levels forms the essential part of the whole<br />
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Abstracts<br />
decommissi<strong>on</strong>ing program. It can help establishing guidelines for the waste classificati<strong>on</strong>, dismantling and demolishing<br />
activities. ORIGEN2 code has l<strong>on</strong>g been in use for computing radi<strong>on</strong>uclide c<strong>on</strong>centrati<strong>on</strong>s in reactor cores and near core<br />
materials for various burn-up-decay cycles, using <strong>on</strong>e-group collapsed cross secti<strong>on</strong>s. Since ORIGEN2 assumes a<br />
c<strong>on</strong>stant flux and nuclide capture cross-secti<strong>on</strong>s in all regi<strong>on</strong>s of the core, uncertainty in its results could increase as<br />
regi<strong>on</strong> of interest goes away from the core. This uncertainty can be removed by using a M<strong>on</strong>te Carlo Code, like MCNP,<br />
for the correct calculati<strong>on</strong>s of flux and capture cross-secti<strong>on</strong>s inside the reactor core and in far core regi<strong>on</strong>s. MCNP has<br />
greater capability to model the reactor problems in much realistic way that is to incorporate geometrical, compositi<strong>on</strong>al<br />
and spectrum informati<strong>on</strong>. In this paper the classificati<strong>on</strong> of radioactive waste from the side structural comp<strong>on</strong>ents of a<br />
CANDU reactor is presented. MCNP model of full core was established because of asymmetric structure of the reactor.<br />
Side structural comp<strong>on</strong>ents of total length 240 cm and radius 16.122 cm were modeled as twelve (12) homogenized cells<br />
of 20 cm length each al<strong>on</strong>g the axial directi<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> neutr<strong>on</strong> flux and <strong>on</strong>e-group collapsed cross-secti<strong>on</strong>s were calculated<br />
by MCNP simulati<strong>on</strong> for each cell, and then those results were applied to ORIGEN2 simulati<strong>on</strong> to estimate nuclide<br />
inventory in the wastes. After retrieving the radiati<strong>on</strong> level of side structural comp<strong>on</strong>ents of in- and ex-core, the<br />
radioactive wastes were classified according to the internati<strong>on</strong>al standards of waste classificati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> wastes from first<br />
and sec<strong>on</strong>d cell of the side structural comp<strong>on</strong>ents were found to exhibit characteristics of class C and Class B wastes<br />
respectively. However, the rest of the waste was found to have activity levels as that of Class A radio-active waste. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
waste is therefore suitable for land disposal in accordance with the internati<strong>on</strong>al standards of waste classificati<strong>on</strong> and<br />
disposal.<br />
4) 40068 – Uranium refining and c<strong>on</strong>versi<strong>on</strong> plant decommissi<strong>on</strong>ing project<br />
Naoki Zaima, Yasuyuki Morimoto, Noritake Sugitsue, Kazumi Kado, JAEA (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> uranium refining and c<strong>on</strong>versi<strong>on</strong> plant at Ningyo-toge (URCP) was c<strong>on</strong>structed in 1981 for the purpose of<br />
dem<strong>on</strong>strati<strong>on</strong> <strong>on</strong> refining and c<strong>on</strong>versi<strong>on</strong> processes from yellow cakes to UF6 via UF4, and then as modified to develop<br />
the c<strong>on</strong>versi<strong>on</strong> of reprocessed uranium producti<strong>on</strong> of natural UF6 and purificati<strong>on</strong> of reprocessed UF6. Through 20 years,<br />
385 t<strong>on</strong>s of natural uranium of UF6 and 336 t<strong>on</strong>s of reprocessed uranium of UF6 had been c<strong>on</strong>ducted. <str<strong>on</strong>g>The</str<strong>on</strong>g>re are two<br />
refining processes in the URCP facilities. One is the wet-type process for the natural uranium and the other is the<br />
dry-type process for the reprocessed uranium. It was found the large amount of uranium residuals such as wet slurry and<br />
dried powder inside the vessels and pipings. Careful c<strong>on</strong>siderati<strong>on</strong> had always been required against the diffusi<strong>on</strong> of<br />
c<strong>on</strong>taminati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> basic policies c<strong>on</strong>cerning plant decommissi<strong>on</strong>ing are the optimizati<strong>on</strong> of the labor costs and the<br />
minimizati<strong>on</strong> of the radioactive wastes. <str<strong>on</strong>g>The</str<strong>on</strong>g> procedures are followings; i)measuring doserate by high sensitivity<br />
surveymeters and identificating nuclide by gamma ray spectrometry, ii)estimating uranium mass inventory, iii) planning<br />
workers distributi<strong>on</strong>s including of radiati<strong>on</strong> c<strong>on</strong>trol staffs, iv)deciding dismantling methods and dec<strong>on</strong>taminating<br />
schematically if required, v)measuring and classifying doserate and c<strong>on</strong>taminati<strong>on</strong> level, vi) managing for radioactive<br />
waste c<strong>on</strong>tainer, vii)c<strong>on</strong>trol for pers<strong>on</strong>al exposures. Through two years and half, almost all equipment had been<br />
dismantled except building dec<strong>on</strong>taminati<strong>on</strong>. Several hundreds t<strong>on</strong>s of dismantled wastes had accumulated in 200 litter<br />
drums approximately. In additi<strong>on</strong>, the sec<strong>on</strong>dary wastes had also been generated. Several thousands day of working time<br />
had spent totally. <str<strong>on</strong>g>The</str<strong>on</strong>g> radiati<strong>on</strong> m<strong>on</strong>itoring of working places had been performed during dismantling, the results were<br />
generally less than 20?Sv/h under the doserate limitati<strong>on</strong>. However, followed by the trace of the reprocessed uranium,<br />
U-232 progenies nuclides such as Th-228 and Tl-208 were observed. <str<strong>on</strong>g>The</str<strong>on</strong>g> expected exposures are apprehensive by<br />
accumulati<strong>on</strong> of the high energy gamma emissi<strong>on</strong> nuclides. For example, the fluidizati<strong>on</strong> media storage tank in which<br />
Th-228 progenies originated from U-232 accumulated. <str<strong>on</strong>g>The</str<strong>on</strong>g>re arises the case of remote c<strong>on</strong>trolled tools for decreasing<br />
pers<strong>on</strong>al exposure if required. As for the waste disposal, the determinati<strong>on</strong> of uranium c<strong>on</strong>tent must be necessary. We are<br />
now developing for measuring systems with better accuracy. <str<strong>on</strong>g>The</str<strong>on</strong>g> further tasks imposed us summarized the followings;<br />
i)dismantling method for high doserate area, ii)reducti<strong>on</strong> of radioactive wastes volume, iii)dec<strong>on</strong>taminati<strong>on</strong> for the<br />
buildings, iv)waste disposal.<br />
5) 40161 – Radiochemical Characterizati<strong>on</strong> of C<strong>on</strong>crete Samples from the Envir<strong>on</strong>ment of Accelerator Facilities<br />
Dorothea Schumann, Paul Scherrer Institute (Switzerland)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Paul Scherrer Institute (PSI) in Switzerland operates the most powerful prot<strong>on</strong> accelerator facility in Europe<br />
and also world-wide, with a beam current of 2 mA and a final prot<strong>on</strong> energy of 590 MeV. It c<strong>on</strong>sists of two injector<br />
cyclotr<strong>on</strong>s with beam energies of 72 MeV each and a ring cyclotr<strong>on</strong> accelerating the prot<strong>on</strong>s to the final energy. Besides<br />
the targets (mainly carb<strong>on</strong> wheels for the mu<strong>on</strong> producti<strong>on</strong> and solid lead as the target for the neutr<strong>on</strong> producti<strong>on</strong>) also<br />
the closer surroundings of the facility are highly activated. One of the comp<strong>on</strong>ents there is c<strong>on</strong>crete which is used in huge<br />
amounts as c<strong>on</strong>structi<strong>on</strong> material for walls and floor and acts as an effective and cheap shielding. Activati<strong>on</strong> of these<br />
comp<strong>on</strong>ents could be neglected in the past because of the relatively low dose rates, but this situati<strong>on</strong> changed with the<br />
upgrade of the accelerator during the last years. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, detailed declarati<strong>on</strong> of the radi<strong>on</strong>uclide c<strong>on</strong>tent is also<br />
requested for c<strong>on</strong>crete from the Swiss authorities (NAGRA). In the present c<strong>on</strong>tributi<strong>on</strong>, we report <strong>on</strong> the radiochemical<br />
analysis of two different kinds of shielding c<strong>on</strong>crete. <str<strong>on</strong>g>The</str<strong>on</strong>g> first samples stem from the floor of a former graphite target<br />
stati<strong>on</strong>, which was dismounted in 1989. Here we expect activati<strong>on</strong> by sec<strong>on</strong>dary neutr<strong>on</strong>s produced by the primary prot<strong>on</strong><br />
beam of 590 MeV from the ring cyclotr<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> sec<strong>on</strong>d series was taken from the envir<strong>on</strong>ment of a copper target hit by 72<br />
MeV prot<strong>on</strong>s from <strong>on</strong>e of the injector cyclotr<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g>se samples were taken in 1998. <str<strong>on</strong>g>The</str<strong>on</strong>g> main activati<strong>on</strong> is also in this<br />
case caused by the produced sec<strong>on</strong>dary neutr<strong>on</strong>s. Besides c<strong>on</strong>venti<strong>on</strong>al gamma-spectrometry, identifying mainly<br />
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Abstracts<br />
lanthanides and 60Co as activati<strong>on</strong> products, also l<strong>on</strong>g-lived radi<strong>on</strong>uclides like 10Be, 26Al, 36Cl and 129I were found to<br />
be present. <str<strong>on</strong>g>The</str<strong>on</strong>g> results of both series are compared. C<strong>on</strong>clusi<strong>on</strong>s for a final disposal can be drawn from the obtained data.<br />
SESSION M2: Public Involvement<br />
1) 40288 – Activities of the OECD/NEA in the Field of Stakeholder C<strong>on</strong>fidence for Radwaste Management and<br />
Decommissi<strong>on</strong>ing<br />
Claudio Pescatore, OECD/NEA<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> OECD/NEA seeks to assist its member countries in developing strategies for the management of all types of<br />
radioactive material, including waste, that are safe and sustainable and that meet the broad needs of society - with<br />
particular emphasis <strong>on</strong> the management of l<strong>on</strong>g-lived waste and spent fuel and <strong>on</strong> decommissi<strong>on</strong>ing of disused nuclear<br />
facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g> programme of work in the area of stakeholder involvement is supervised by the Radioactive Waste<br />
Management Committee (RWMC) and carried out by its Forum <strong>on</strong> Stakeholder C<strong>on</strong>fidence (FSC). <str<strong>on</strong>g>The</str<strong>on</strong>g> latter is made of<br />
senior representatives from regulatory authorities, decommissi<strong>on</strong>ing organisati<strong>on</strong>s, policy making bodies, and<br />
research-anddevelopment instituti<strong>on</strong>s from the NEA countries. First and foremost, the FSC is a “learning organisati<strong>on</strong>”.<br />
Through the FSC, members seek to improve themselves as resp<strong>on</strong>sive actors in the governance of radioactive waste<br />
management and decommissi<strong>on</strong>ing. Delegates attend in order to benefit from in-depth pragmatic exchanges with both<br />
peers and stakeholders bey<strong>on</strong>d the membership. <str<strong>on</strong>g>The</str<strong>on</strong>g>y then c<strong>on</strong>solidate their learning: the FSC takes as a resp<strong>on</strong>sibility to<br />
mature its less<strong>on</strong>s in discussi<strong>on</strong> and cooperati<strong>on</strong> with those c<strong>on</strong>cerned, and then to validate its c<strong>on</strong>clusi<strong>on</strong>s with the help<br />
of academic researchers. <str<strong>on</strong>g>The</str<strong>on</strong>g> third step in the cycle is to make the learning available to others. <str<strong>on</strong>g>The</str<strong>on</strong>g> FSC has held<br />
workshops in six countries and local communities therein according to its own well tested approach. In each place, the<br />
host defines the principal themes for discussi<strong>on</strong> in radioactive waste management. FSC members learn from nati<strong>on</strong>al<br />
presenters about the history and c<strong>on</strong>text of each case study and hear a broad range of stakeholder voices describe their<br />
positi<strong>on</strong>, acti<strong>on</strong>s and c<strong>on</strong>cerns. Sitting together in small groups for roundtable discussi<strong>on</strong>s, FSC members can ask<br />
questi<strong>on</strong>s of hosting stakeholders, understand better their point of view, and share experience from their own instituti<strong>on</strong>s<br />
and countries. Each table then gives feedback to the entire audience, and the main observati<strong>on</strong>s are published al<strong>on</strong>gside<br />
the texts of stakeholder presentati<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> FSC then elaborates further <strong>on</strong> the less<strong>on</strong>s to be learnt. Over the 10 years of its<br />
existence, the FSC has established itself as a key internati<strong>on</strong>al player and adviser in the field of stakeholder c<strong>on</strong>fidence.<br />
Its numerous studies and its advice are available <strong>on</strong>-line in the form, respectively, of academic reports and policy<br />
brochures and flyers. Explored topics include: stepwise decisi<strong>on</strong>-making, principles for stakeholders involvement, the<br />
partnering approach for siting and developing fuel cycle facilities, less<strong>on</strong>s learned in decommissi<strong>on</strong>ing, providing<br />
value-added in view of building a durable relati<strong>on</strong>ship between a facility and its host community, etc. Current study areas<br />
include: the interests and roles of regi<strong>on</strong>al authorities, how to increase the knowledge base of journalists, and providing<br />
added value (bey<strong>on</strong>d ec<strong>on</strong>omic benefits) to communities hosting waste management facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g> activities and less<strong>on</strong>s<br />
to be learnt will be reviewed for the ICEM-2010 audience.<br />
2) 40219 – A Comparative Study of Stakeholder Participati<strong>on</strong> in the Cleanup of Radioactive Wastes in the US,<br />
Japan and UK<br />
Mito Akiyoshi, Senshu University (Japan); William Lawless, Fjorentina Angjellari-Dajci, Paine College (USA);<br />
Christian Poppeliers, Augusta State University (USA); John Whitt<strong>on</strong>, Nati<strong>on</strong>al Nuclear Laboratory (UK)<br />
We review case studies of stakeholder participati<strong>on</strong> in the envir<strong>on</strong>mental cleanup of radioactive wastes in the USA,<br />
Japan and UK (e.g., [21,26,27,66,78]). Citizen participati<strong>on</strong> programs in these three countries are at different stages:<br />
mature in the US, starting in Japan, and becoming operati<strong>on</strong>al in the UK. <str<strong>on</strong>g>The</str<strong>on</strong>g> US issue at the US Department of Energy’s<br />
(DOE) Savannah River Site (SRS) in South Carolina (SC) had been focused <strong>on</strong> citizens encouraging Federal (DOE; US<br />
Envir<strong>on</strong>mental Protecti<strong>on</strong> Agency, or EPA; and the US Nuclear Regulatory Commissi<strong>on</strong>, or NRC) and State (SC's<br />
Department of Health and Envir<strong>on</strong>mental Compliance, or DHEC) agencies to pursue "Plug-in-RODs" at SRS to simplify<br />
the regulati<strong>on</strong>s to accelerate closing seepage basins at SRS. In Japan, the Reprocessing of spent fuel and deep geological<br />
disposal of vitrified high-level waste have been am<strong>on</strong>g Japan's priorities. A reprocessing plant in Rokkasho, Aomori<br />
Prefecture is expected to commence operati<strong>on</strong>s in October 2010. <str<strong>on</strong>g>The</str<strong>on</strong>g> search of a site for a deep geological disposal<br />
facility has been <strong>on</strong>going since 2002. But the direct engagement of stakeholders has not occurred in Japan. Indirectly,<br />
stakeholders attempt to exert influence <strong>on</strong> decisi<strong>on</strong>-making with social movements, local electi<strong>on</strong>s, and litigati<strong>on</strong>. In the<br />
UK, the issue is gaining effective citizen participati<strong>on</strong> with the UK's Nuclear Decommissi<strong>on</strong>ing Authority (NDA). We<br />
hope that the case studies from these countries may improve citizen participati<strong>on</strong>.<br />
3)� 40076 – Territorial Integrati<strong>on</strong> of the Geological Repository in France<br />
Gerald Ouzounian, Sebastien Farin, Roberto Miguez, Jean-Louis Tis<strong>on</strong>, Andra (France)<br />
In France, a framework has been drawn up by the Nati<strong>on</strong>al Assembly and implemented by the government, in order<br />
to get the best relati<strong>on</strong>ship between Andra, am<strong>on</strong>g others, and the stakeholders and the inhabitants of the towns and<br />
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countries where disposal facilities or projects are or could be established. <str<strong>on</strong>g>The</str<strong>on</strong>g> main threads of the two Acts passed* in<br />
2006, being relevant to the relati<strong>on</strong>ship with inhabitants are the informati<strong>on</strong> exchange and the local ec<strong>on</strong>omic<br />
development. Dealing with the informati<strong>on</strong> exchange and diffusi<strong>on</strong>: - <str<strong>on</strong>g>The</str<strong>on</strong>g> Local Informati<strong>on</strong> Committee (CLI), for each<br />
nuclear facility, has been reinforced and a specific, Local Informati<strong>on</strong> and Oversight Committee (for the Underground<br />
Laboratory in Meuse-Haute-Marne) has been renewed. <str<strong>on</strong>g>The</str<strong>on</strong>g> CLI was in charge of a general assignment to inform and<br />
c<strong>on</strong>sult <strong>on</strong> nuclear safety, radioprotecti<strong>on</strong> and envir<strong>on</strong>mental topics. Now, since 2006, the nuclear facility’s CLI and the<br />
CLIS are able to order study reports, measures and analyses to experts freely selected. - Creati<strong>on</strong> of the High Committee<br />
for Transparency and Informati<strong>on</strong> <strong>on</strong> Nuclear Safety (HCTISN). This new authority aims to inform, c<strong>on</strong>sult and debate<br />
about the risks relevant to nuclear activities and their impacts <strong>on</strong> people’s health, envir<strong>on</strong>ment and nuclear safety. Andra<br />
c<strong>on</strong>tributes to the functi<strong>on</strong>ing of CLI in disposal facilities at Manche and Aube Departments, and CLIS of the<br />
underground Laboratory at Meuse and Haute-Marne departments. This paper will present these c<strong>on</strong>tributi<strong>on</strong>s and how<br />
Andra’s acti<strong>on</strong> helps to reach the goals of informati<strong>on</strong> and exchange with the people around its facilities. C<strong>on</strong>cerning the<br />
local ec<strong>on</strong>omic development, there are specific organizati<strong>on</strong>s or schemes, depending <strong>on</strong> the facility.: - Local taxes<br />
c<strong>on</strong>tributi<strong>on</strong>s based <strong>on</strong> the disposal facilities activities as is usual in France. - A High Level Committee (CHN) and two<br />
public interest groups (GIP) in Meuse and Haute-Marne departments have been set up since 1991 and 2005. Andra is<br />
represented in these three instituti<strong>on</strong>s, but they are not funded at all by Andra. This paper will show the Andra’s<br />
involvement in the local ec<strong>on</strong>omic and territorial developments. Within this general framework Andra has developed<br />
informati<strong>on</strong> and exchanges acti<strong>on</strong>s with the stakeholders and the inhabitants around its facilities. Examples of these<br />
acti<strong>on</strong>s will be presented also. (*) -Planning Act No. 2006-739 of 28 June 2006 c<strong>on</strong>cerning the sustainable Management<br />
of Radioactive materials an waste. - Act No. 2006-686 of 13 June 2006 <strong>on</strong> Transparency and Security in the Nuclear<br />
Field.<br />
4)� 40256 – Public Involvement in the Closure of Fernald<br />
John Bradburne, Bradburne C<strong>on</strong>sulting LLC (USA)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> closure of Fernald set the standard for public involvement in reaching an envir<strong>on</strong>mentally acceptable end state<br />
for DOE sites. All stakeholders including the client (DOE), workforce, residents, state regulators and Federal regulators<br />
were engaged in determining the path to closure and what endstate at closure would be acceptable.<br />
SESSION L8: L/ILW Poster<br />
1) 40006 – A GoldSim Modeling Approach to Safety Assessment of an LLW Repository System<br />
Youn Myoung Lee, J<strong>on</strong>gtae Je<strong>on</strong>g, J<strong>on</strong>gw<strong>on</strong> Choi, KAERI (Korea Rep.)<br />
An assessment program for the safety assessment and performance evaluati<strong>on</strong> of a low- and intermediate level<br />
waste (LILW) repository system has been developed by utilizing GoldSim, by which nuclide transports in the near- and<br />
far-field of a repository as well as a transport through a biosphere under various natural and manmade disruptive events<br />
affecting a nuclide release could be modeled and evaluated. To dem<strong>on</strong>strate its usability, some illustrative cases under the<br />
selected scenarios including the influence of degradati<strong>on</strong> of man-made barriers and the possible disruptive events caused<br />
by an accidental human intrusi<strong>on</strong> or an earthquake have been investigated and illustrated for a hypothetical LILW<br />
repository. Even though all the parameter values applied to a hypothetical repository are assumed without any real base,<br />
the illustrative cases are very informative especially when seeing the result of the probabilistic calculati<strong>on</strong> with scenarios<br />
which are possibly happen for nuclide release and further transport in and around the repository system.<br />
2) 40011 – Gas Migrati<strong>on</strong> Mechanism of Saturated Highly-compacted Bent<strong>on</strong>ite and its Modeling<br />
Yukihisa Tanaka, Michihiko Hir<strong>on</strong>aga, Koji Kudo, CRIEPI (Japan)<br />
In the current c<strong>on</strong>cept of repository for radioactive waste disposal, compacted bent<strong>on</strong>ite will be used as an<br />
engineered barrier mainly for inhibiting migrati<strong>on</strong> of radioactive nuclides. Hydrogen gas can be generated inside the<br />
engineered barrier by anaerobic corrosi<strong>on</strong> of metals used for c<strong>on</strong>tainers, etc. If the gas generati<strong>on</strong> rate exceeds the<br />
diffusi<strong>on</strong> rate of gas molecules inside of the engineered barrier, gas will accumulate in the void space inside of the<br />
engineered barrier until its pressure becomes large enough for it to enter the bent<strong>on</strong>ite as a discrete gaseous phase. It is<br />
expected to be not easy for gas to entering into the bent<strong>on</strong>ite as a discrete gaseous phase because the pore of compacted<br />
bent<strong>on</strong>ite is so minute. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore the gas migrati<strong>on</strong> tests are c<strong>on</strong>ducted in this study to investigate the mechanism of gas<br />
migrati<strong>on</strong>. On the basis of the experimental facts obtained through the gas migrati<strong>on</strong> tests, possible gas migrati<strong>on</strong><br />
mechanism is proposed. A simplified method for calculating gas pressure at large breakthrough, which is defined as a<br />
sudden and sharp increase in gas flow rate out of the specimen is also proposed.<br />
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3) 40012 – Development of numerical simulati<strong>on</strong> method for gas migrati<strong>on</strong> through highly-compacted bent<strong>on</strong>ite<br />
using model of two-phase flow through deformable porous media<br />
Yukihisa Tanaka, CRIEPI (Japan)<br />
In the current c<strong>on</strong>cept of repository for radioactive waste disposal, compacted bent<strong>on</strong>ite will be used as an<br />
engineered barrier mainly for inhibiting migrati<strong>on</strong> of radioactive nuclides. Hydrogen gas can be generated inside of the<br />
engineered barrier by anaerobic corrosi<strong>on</strong> of metals used for c<strong>on</strong>tainers, etc. It is expected to be not easy for gas to<br />
entering into the bent<strong>on</strong>ite as a discrete gaseous phase because the pore of compacted bent<strong>on</strong>ite is so minute. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore it<br />
is necessary to investigate the effect of gas pressure generati<strong>on</strong> and gas migrati<strong>on</strong> <strong>on</strong> the engineered barrier, peripheral<br />
facilities and ground. In this study, a method for simulating gas migrati<strong>on</strong> through the compacted bent<strong>on</strong>ite is proposed.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> proposed method can analyze coupled hydrological-mechanical processes using the model of two-phase flow<br />
through deformable porous media. Validity of the proposed analytical method is examined by comparing gas migrati<strong>on</strong><br />
test results with the calculated results, which revealed that the proposed method can simulate gas migrati<strong>on</strong> behavior<br />
through compacted bent<strong>on</strong>ite with accuracy.<br />
4) 40020 – Planning of Large-scale In-situ Gas Generati<strong>on</strong> Experiment in Korean Radioactive Waste Repository<br />
Juyoul Kim, Sukho<strong>on</strong> Kim, FNC Technology Co.(Korea Rep.);<br />
Jinbeak Park, Sungjoung Lee, KRMC (Korea Rep.)<br />
In the Korean LILW (Low- and Intermediate-Level radioactive Waste) repository at the Gye<strong>on</strong>gju site, the<br />
degradati<strong>on</strong> of organic wastes and the corrosi<strong>on</strong> of metallic wastes and steel c<strong>on</strong>tainers would be important processes that<br />
a?ect repository geochemistry, speciati<strong>on</strong> and transport of radi<strong>on</strong>uclides during the lifetime of a radioactive waste<br />
disposal facility.<br />
Gas is generated in associati<strong>on</strong> with these processes and has the potential to pressurize the repository, which can<br />
promote the transport of groundwater and gas, and c<strong>on</strong>sequently radi<strong>on</strong>uclide transport. Microbial activity plays an<br />
important role in organic degradati<strong>on</strong>, corrosi<strong>on</strong> and gas generati<strong>on</strong> through the mediati<strong>on</strong> of reducti<strong>on</strong>–oxidati<strong>on</strong><br />
reacti<strong>on</strong>s.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Korean research project <strong>on</strong> gas generati<strong>on</strong> will be performed by Korea Radioactive Waste Management<br />
Corporati<strong>on</strong> (KRMC). A large-scale in-situ experiment will form a central part of the project, where gas generati<strong>on</strong> in<br />
real radioactive low-level maintenance waste from nuclear power plants will be studied.<br />
In order to examine gas generati<strong>on</strong> from an LILW repository which is being c<strong>on</strong>structed at present by 2012, two<br />
large-scale facilities for the gas generati<strong>on</strong> experiment (GGE) will be established, each equipped with a c<strong>on</strong>crete<br />
c<strong>on</strong>tainer for 16 or 9 drums of LILW from Korean nuclear power plants. Each c<strong>on</strong>tainer will be enclosed within a<br />
gas-tight and acid-proof steel tank. <str<strong>on</strong>g>The</str<strong>on</strong>g> experiment facility will be filled with ground water that provides representative<br />
chemical c<strong>on</strong>diti<strong>on</strong>s and microbial inoculati<strong>on</strong> in the repository near field.<br />
In the experiment, the design includes l<strong>on</strong>g-term m<strong>on</strong>itoring for the rate and compositi<strong>on</strong> of gas generated, and<br />
aqueous geochemistry and microbe populati<strong>on</strong>s present at various locati<strong>on</strong>s through <strong>on</strong>-line analyzers and manual<br />
sampling.<br />
A main schedule for establishing the experiment facility is as follows: Completi<strong>on</strong> of the detailed design until the<br />
sec<strong>on</strong>d quarter of the year 2010; Completi<strong>on</strong> of the manufacture and <strong>on</strong>-site installati<strong>on</strong> until the sec<strong>on</strong>d quarter of the<br />
year 2011; Start of the operati<strong>on</strong> and m<strong>on</strong>itoring from the third quarter of the year 2011.<br />
5) 40024 – Estimati<strong>on</strong> and measurement of porosity change in cement paste<br />
Euny<strong>on</strong>g Lee, Haeryojng Jung, Ki-jung Kw<strong>on</strong>, KRMC (Korea Rep.);<br />
Do-Gyeum Kim, Korea Institute of C<strong>on</strong>structi<strong>on</strong> Technology (Korea Rep.)<br />
Laboratory-scale experiments were performed to understand the porosity change of cement pastes. <str<strong>on</strong>g>The</str<strong>on</strong>g> cement<br />
pastes were prepared using commercially available Type-I ordinary Portland cement (OPC). As the cement pastes were<br />
exposed in water, the porosity of the cement pastes sharply increased; however, the slow decrease of porosity was<br />
observed as the dissoluti<strong>on</strong> period was extended more than 50 days. As expected, the dissoluti<strong>on</strong> reacti<strong>on</strong> was<br />
significantly influenced by w/c raito and the i<strong>on</strong>ic strength of soluti<strong>on</strong>. A thermodynamic model was applied to simulate<br />
the porosity change of the cement pastes. It was highly influenced by the depth of the cement pastes. <str<strong>on</strong>g>The</str<strong>on</strong>g>re was porosity<br />
increase <strong>on</strong> the surface of the cement pastes due to dissoluti<strong>on</strong> of hydrati<strong>on</strong> products, such as portlandite, ettringite, and<br />
CSH. However, the decrease of porosity was estimated inside the cement pastes due to the precipitati<strong>on</strong> of cement<br />
minerals.<br />
6) 40082 – Separati<strong>on</strong> and Recovery of Sodium Nitrate from Low-level Radioactive Liquid Waste by<br />
Electrodialysis<br />
Yoshihiro Meguro, A Kato, Y Watanabe, Kuniaki Takahashi, JAEA (Japan)<br />
Low-level radioactive liquid wastes including TRU elements have been generated from several treatments in<br />
reprocessing facilities. <str<strong>on</strong>g>The</str<strong>on</strong>g>se wastes usually include highly c<strong>on</strong>centrated sodium nitrate. In Japan the liquid wastes are<br />
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Abstracts<br />
planned to dispose in geological layer with HLW following solidificati<strong>on</strong> of them and in this plan it is c<strong>on</strong>sidered that<br />
leached nitrate from the solidified materials and its decompositi<strong>on</strong> products would change sorpti<strong>on</strong> coefficients of<br />
radi<strong>on</strong>uclides and then their migrati<strong>on</strong> in the l<strong>on</strong>g-term would be influenced. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore a method to remove the nitrate<br />
i<strong>on</strong>s prior to the solidificati<strong>on</strong> is required. <str<strong>on</strong>g>The</str<strong>on</strong>g> authors have been developed a separati<strong>on</strong> and recovery method of sodium<br />
nitrate from the low-level radioactive liquid waste by using an electrodialysis method not <strong>on</strong>ly to remove the nitrate but<br />
also to reduce waste volume and to reuse resources. Here, nitrate i<strong>on</strong> is recovered as nitric acid and sodium i<strong>on</strong> as sodium<br />
hydroxide through i<strong>on</strong>-exchange membranes. Especially, a ceramic cati<strong>on</strong>-exchange membrane, in which sodium i<strong>on</strong> was<br />
selectively transported, was employed to prevent c<strong>on</strong>taminati<strong>on</strong> of radioactive nuclides in the recovered sodium<br />
hydroxide. And also an ani<strong>on</strong>-exchange membrane, in which m<strong>on</strong>ovalent ani<strong>on</strong>s were selectively transported ani<strong>on</strong>s, was<br />
employed to improve the nitric acid purity. In the present paper, we showed our recent results of investigati<strong>on</strong> for<br />
transport efficiency of the target i<strong>on</strong>s through the membranes and their selectivity. Aqueous soluti<strong>on</strong>s of 5 mol/L sodium<br />
nitrate c<strong>on</strong>taining a small amount of potassium, cesium, and str<strong>on</strong>tium i<strong>on</strong>s or c<strong>on</strong>taining nitrite, carb<strong>on</strong>ate, sulfate, and<br />
phosphate i<strong>on</strong>s were prepared as simulated waste soluti<strong>on</strong>s. As a sodium-selective cati<strong>on</strong>-exchange membrane,<br />
NaSICON membrane produced by Ceramatec Inc. was employed and NEOSEPTA ACS membrane produced by<br />
ASTOM Co. as a m<strong>on</strong>o-ani<strong>on</strong> permselective membrane. Sodium i<strong>on</strong>s were transferred through the NaSICON membrane<br />
as much as the quantity of electricity used in the electrodialysis, but <strong>on</strong>ly hundredth to 10thousandth amount of potassium,<br />
cesium, and str<strong>on</strong>tium were transferred through the membrane. <str<strong>on</strong>g>The</str<strong>on</strong>g> sodium i<strong>on</strong>s could be effectively and selectively<br />
removed from the highly c<strong>on</strong>centrated soluti<strong>on</strong> using the NaSICON membrane. Through the ACS membrane m<strong>on</strong>ovalent<br />
ani<strong>on</strong>s were efficiently transferred, but less than 10% of multivalent ani<strong>on</strong>s were moved at which 90% nitrate was. It was<br />
c<strong>on</strong>firmed from these results that the electrodialysis method with the i<strong>on</strong>-selective membranes was useful procedure to<br />
remove and recover sodium nitrate from the liquid waste. This work was funded by ANRE: Agency for Natural<br />
Resources and Energy, of METI: Ministry of Ec<strong>on</strong>omy, Trade and Industry, of Japan.<br />
7) 40109 – Study <strong>on</strong> Mechanical Influence of Gas Generati<strong>on</strong> and Migrati<strong>on</strong> <strong>on</strong> Engineered Barrier System in<br />
adioactive Waste Disposal Facility<br />
Mamoru Kumagai, JNFL (Japan); Shuichi Yamamoto, Kunifumi Takeuchi, Obayashi Corporati<strong>on</strong> (Japan);<br />
Yukihisa Tanaka, Michihiko Hir<strong>on</strong>aga, CRIEPI (Japan)<br />
In Japan, some radioactive waste with a relatively higher radioactivity c<strong>on</strong>centrati<strong>on</strong> from nuclear facilities is to be<br />
packaged in rectangle steel c<strong>on</strong>tainers and disposed of in sub-surface disposal facilities, where normal human intrusi<strong>on</strong><br />
rarely occurs. After the closure of a facility, its pore is saturated with groundwater. If the dissolved oxygen of the pore<br />
water is c<strong>on</strong>sumed by steel corrosi<strong>on</strong>, hydrogen gas will be generated from the metallic waste, steel c<strong>on</strong>tainers, and<br />
reinforcing bars of c<strong>on</strong>crete mainly by anaerobic corrosi<strong>on</strong>. If the generated gas accumulates and the gas pressure<br />
increases excessively in the facility, the facility’s barrier performance might be degraded by mechanical influences such<br />
as crack formati<strong>on</strong> in cementitious material or deformati<strong>on</strong> of bent<strong>on</strong>ite material.<br />
Firstly, in this study, we assessed the time evoluti<strong>on</strong> of the gas pressure and the water saturati<strong>on</strong> in a sub-surface<br />
disposal facility by using a multi-phase flow numerical analysis code, GETFLOWS, in which a pathway dilati<strong>on</strong> model is<br />
introduced and modified in order to reproduce the gas migrati<strong>on</strong> mechanism through the highly compacted bent<strong>on</strong>ite.<br />
Next, we calculated the stress applied to the engineered barriers of the facility from the results of the time evoluti<strong>on</strong><br />
of the pressure and the saturati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g>n, we c<strong>on</strong>ducted a mechanical stability analysis of the engineered barriers by using<br />
a n<strong>on</strong>linear finite element code, ABAQUS, in order to evaluate their performances after the closure of the facility.<br />
8) 40192 – Liquid Radioactive Wastes in the Republican Point of Burial Radioactive Waste of Tajikistan<br />
Nazirzh<strong>on</strong> Buriev, Physical-Technical Institute of the Academy of Sciences (Tajikistan)<br />
Liquid radioactive wastes (LRW), as different from the solid <strong>on</strong>es, have unstable structure and occupy fairly big<br />
spaces, requiring serious attenti<strong>on</strong> to be paid to them and relatively big expenses for arrangement of their storage,<br />
transportati<strong>on</strong> and disposal. Because of their unstable nature, the LRW c<strong>on</strong>stitute great hazards for envir<strong>on</strong>ment and<br />
human ecosystem. Under implementati<strong>on</strong> of the <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Scientific and Technical Center (ISTC) Project ?1082.3 «<br />
Inspecti<strong>on</strong> of Republican Point of Burial Radioactive Wastage with the Purpose of Development of the Technical<br />
Decisi<strong>on</strong> <strong>on</strong> its Rehabilitati<strong>on</strong> », in accordance with the work plan, there has been projected selecti<strong>on</strong> of samples from the<br />
c<strong>on</strong>tainer for storage of liquid radioactive wastes (LRW), their radiometric and spectral studies, and making decisi<strong>on</strong>s for<br />
LRW further treatment and disposal. Preliminary surveys of the c<strong>on</strong>tainer for storage of LRW revealed that the volume<br />
of the c<strong>on</strong>tainer is 200m3. LRW in the c<strong>on</strong>tainer were brought and received for disposals from 1967 till 1974 years. At<br />
present time, the volume of LRW in the c<strong>on</strong>tainer is around 120m3. In accordance with account documents, the general<br />
activity of LRW in the c<strong>on</strong>tainer makes approximately 0,5 Cu, but these data may be not correct. Activity Indices of<br />
LRW Stored in the C<strong>on</strong>tainer Index Specific Activity (Bk/l) Total Activity (Bk) Withdrawal Level (Bk) ? ? 30 3.6 ? 106<br />
- ? ? 2100 25.2 ? 107 - 137Cs 670 804 ? 105 1 ? 104 226Ra 30 3.6 ? 106 1 ? 104 90Sr 1700 2.0 ? 107 1 ? 104 60?? 5.2<br />
6.24 ? 105 1 ? 105 3? 2.5 ? 103 3.0 ? 108 1 ? 109 40? 1.6 1.92 ? 105 1 ? 106<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> tabled data allow to making the following c<strong>on</strong>clusi<strong>on</strong>s: 1. During the l<strong>on</strong>g storage of LRW, there turned to<br />
occur gravitati<strong>on</strong>al stratificati<strong>on</strong> in the c<strong>on</strong>tainer, with the LRW being stratified for liquid, bottom gels and solid<br />
sedimentati<strong>on</strong>; bottom sedimentati<strong>on</strong> c<strong>on</strong>tain both, big particles (more than 0.5 mm) and small particles (less than 0.5<br />
mm). 2. Radioactive substances may be in the form of water-soluble i<strong>on</strong>s, gels and solid particles. Gas layer over the<br />
liquid may have c<strong>on</strong>siderable c<strong>on</strong>tent of rad<strong>on</strong>. 3. As to specific activity, the liquid may be c<strong>on</strong>sidered as a low-active<br />
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Abstracts<br />
radioactive substance. At the same time, gels and bottom sedimentati<strong>on</strong> may have high levels of radioactivity. Under the<br />
project implementati<strong>on</strong>, there has been developed a c<strong>on</strong>tact-free sucti<strong>on</strong> way of sampling from the c<strong>on</strong>tainer for storage<br />
of LRW. <str<strong>on</strong>g>The</str<strong>on</strong>g>re has been designed a unit for taking samples from different depths in the c<strong>on</strong>tainer and placing them into a<br />
special vessel for their storage and transportati<strong>on</strong>. Results of analyses of physical, chemical, radiometric and spectral<br />
features of the selected samples will allow to development of a technology for the c<strong>on</strong>tainer c<strong>on</strong>tent dec<strong>on</strong>taminati<strong>on</strong> and<br />
transformati<strong>on</strong> of radioactivity of LRW stored in the c<strong>on</strong>tainer into a stable and compact form for their further disposal.<br />
9) 40197 – Inspecti<strong>on</strong> of Burial Points of Radioactive Waste in the Republic of Tajikistan<br />
Nazirzh<strong>on</strong> Buriev,Physical-Technical Institute of the Academy of Sciences (Tajikistan);<br />
Akram Juraev, Dzhamshed Abdushukurov,<br />
S.U.Umarov Physical Technical Institute of Academy of Sciences of Republic of Tajikistan, (Tajikistan)<br />
Under implementati<strong>on</strong> of the <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Scientific and Technical Center (ISTC) Project ?1082.3 « Inspecti<strong>on</strong> of<br />
Republican Point of Burial Radioactive Wastage with the Purpose of Development of the Technical Decisi<strong>on</strong> <strong>on</strong> its<br />
Rehabilitati<strong>on</strong> », there has been made a survey of the radioactive waste disposal sites in the RPBRW area for the whole<br />
period of its activity, starting from 1962 and up to the present time. Before commencement of practical surveys, we had<br />
studied the following: the RPBRW documentati<strong>on</strong>, foundati<strong>on</strong> history, geographical locati<strong>on</strong>, seismic and climatic<br />
c<strong>on</strong>diti<strong>on</strong>s of the area, engineering and technical documentati<strong>on</strong>, history of previous radioactive waste disposals and the<br />
present state of affairs. <str<strong>on</strong>g>The</str<strong>on</strong>g>re had been arranged meetings and interviews with the RPBRW officers and workers, during<br />
which informati<strong>on</strong> of interest was collected. <str<strong>on</strong>g>The</str<strong>on</strong>g>re had been made a gamma- and neutr<strong>on</strong>-survey of all the RPBRW<br />
facilities located in the Center’s restricted, c<strong>on</strong>trolled and observati<strong>on</strong> z<strong>on</strong>es. Results of the surveys are provided in the<br />
form of figures put <strong>on</strong> the facility routing survey maps. During the surveys, there had been selected samples of soils, silts,<br />
vegetati<strong>on</strong>, sewage waters, atmospheric precipitati<strong>on</strong> and tap water throughout the RPBRW area. In particular, there had<br />
been selected: in the restricted z<strong>on</strong>e – 109 samples, in the c<strong>on</strong>trolled z<strong>on</strong>e – 13 samples, in the observati<strong>on</strong> z<strong>on</strong>e – 91<br />
samples, and in the adjacent territory – 22 samples. In total, there were taken 235 samples out of which: soils – 210<br />
samples, vegetati<strong>on</strong> – 10 samples, silts – 2 samples, sewage waters – 10 samples, tap water – 2 samples, and snow – 1<br />
sample. All the samples were selected, packed, marked, and transported to laboratory to prepare them for radiometric and<br />
spectral studies in strict observance of the methodical guidelines developed. <str<strong>on</strong>g>The</str<strong>on</strong>g> tests were made by means of HPG<br />
detector manufactured by a firm “Canberra”. In the restricted z<strong>on</strong>e, soil samples were taken from the surface as well as<br />
from pits, to trace soil migrati<strong>on</strong> of radi<strong>on</strong>uclides. Pits were dug out up to 2m deep around radioactive waste disposal<br />
sites down the slope of a hill. <str<strong>on</strong>g>The</str<strong>on</strong>g>re are no open water sources in the RPBRW area. We selected precipitati<strong>on</strong> waters<br />
flowing across the RPBRW area, which may bear important informati<strong>on</strong> <strong>on</strong> radiati<strong>on</strong> situati<strong>on</strong>. Samples were taken in the<br />
spring time right after raining. Selecti<strong>on</strong> points were atmospheric precipitati<strong>on</strong> drains and natural collectors near the<br />
RPBRW facilities. On the same sites there were taken the samples of silt borne by waste waters. Vegetati<strong>on</strong> samples<br />
were annual grasses and bushes thriving in the RPBRW area, as well as arboraceous samples (acacia tree). To trace<br />
possible migrati<strong>on</strong> of radi<strong>on</strong>uclides into the trunk of a tree growing in the close vicinity of the radioactive waste disposal<br />
site, there had been taken samples of its bark, trunk, small annual branches and leaves. Results of the sample laboratory<br />
tests are incorporated into the Project T-1082.3 general database compiled as tables in Microsoft Office Excel format.<br />
10) 40198 – Pre-treatment Method of Powder Waste for Vitrificati<strong>on</strong><br />
Deun-Man Kim, Hyun-Je Cho, J<strong>on</strong>g-Kil Park, Nuclear Engineering & Technology Institute (Korea Rep.)<br />
Solidificati<strong>on</strong> techniques to reduce the volume of the waste have been developed using binder materials such as<br />
cement, paraffin, and polymer. A vitrifying technique that realizes high volume reducti<strong>on</strong> and stably c<strong>on</strong>fines<br />
radioactivity within the glass material was researched with dried powder waste. Boric acid waste in PWRs is dried <strong>on</strong><br />
C<strong>on</strong>centrated Waste Dry System (CWDS). In the case of feeding the powder wastes into a cold crucible inducti<strong>on</strong> melter<br />
without pre-treatment, there is a possibility that the powder waste may enter the off-gas treatment system before mixture<br />
with melted glass and the feeding pipes could be clogged because of accumulati<strong>on</strong> of these waste. A method to pre-treat<br />
the c<strong>on</strong>centrated waste by pelletizing powder waste was studied for a vitrificati<strong>on</strong> process. Final products were satisfied<br />
with the requirements of hardness and friability. This research presents the pretreatment method of powder waste to<br />
apply <strong>on</strong> vitrificati<strong>on</strong> facilities.<br />
11) 40208 – Characterizati<strong>on</strong> and Pre-treatment of LLW in Turkey<br />
Ahmet Erdal Osmanlioglu, Turkish Atomic Energy Authority (Turkey)<br />
Pre-treatment of radioactive waste is the first step in waste management program that occurs after waste generati<strong>on</strong><br />
from various applicati<strong>on</strong>s in Turkey. Pre-treatment and characterizati<strong>on</strong> practices are carried out in Radioactive Waste<br />
Management Unit (RWMU) at Cekmece Nuclear Research and Training Center (CNRTC) in Istanbul. This facility has<br />
been assigned to take all low-level radioactive wastes generated by nuclear applicati<strong>on</strong>s in Turkey. <str<strong>on</strong>g>The</str<strong>on</strong>g> wastes are<br />
generated from research and nuclear applicati<strong>on</strong>s mainly in medicine, biology, agriculture, quality c<strong>on</strong>trol in metal<br />
processing and c<strong>on</strong>structi<strong>on</strong> industries. <str<strong>on</strong>g>The</str<strong>on</strong>g>se wastes are classified as low- level radioactive wastes. Pre-treatment<br />
practices cover several steps. In this paper, main steps of pre-treatment and characterizati<strong>on</strong> are presented. Basically these<br />
are; collecti<strong>on</strong>, segregati<strong>on</strong>, chemical adjustment, size reducti<strong>on</strong> and dec<strong>on</strong>taminati<strong>on</strong> operati<strong>on</strong>s.<br />
100
Abstracts<br />
12) 40221 – Dec<strong>on</strong>taminati<strong>on</strong> of Radioactive C<strong>on</strong>crete Wastes by <str<strong>on</strong>g>The</str<strong>on</strong>g>rmal and Mechanical Processes<br />
B.Y. Min, Ki W<strong>on</strong> Lee, Un Soo Chung, W.K Choi, Kune-Woo Lee, KAERI (Korea Rep.)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> purpose of this paper is to provide the results of a series of volume reducti<strong>on</strong> tests c<strong>on</strong>sucted in thermal and<br />
mechanical processes. Korea Atomic Energy Research Institites (KAERI) has developed volume reducti<strong>on</strong> technology<br />
applocable to an activated heavy c<strong>on</strong>crete waste generated by dismantled Korea research reactor 2 (KRR-2) and a<br />
uranium c<strong>on</strong>versi<strong>on</strong> plant (UCP). the volume reductuin could be achieved above 70% by lab scale test by thermal and<br />
mechanical separati<strong>on</strong> processes. Pilot test were performed with radioactively c<strong>on</strong>taninated dismantled c<strong>on</strong>crete waste.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> developed processes were quite effective for volume reducti<strong>on</strong> of radioactively c<strong>on</strong>taminated dismantled c<strong>on</strong>crete<br />
waste.<br />
13) 40302 – Latex Particles Functi<strong>on</strong>alized with Transiti<strong>on</strong> Metals Ferrocyanides for Cesium Uptake and<br />
Dec<strong>on</strong>taminati<strong>on</strong> of Solid Bulk Materials<br />
Dmitry Marinin, Valentin Avramenko, Dmitry Marinin, Valentin Sergienko,<br />
Institute of Chemistry FEDRAS (Russia);<br />
Veniamin Zheleznov, Irina Sheveleva, Russian Academy of Sciences (Russia)<br />
Dec<strong>on</strong>taminati<strong>on</strong> of spent i<strong>on</strong>-exchange resins, corrosi<strong>on</strong>-unstable metal structures, soil, ground, and c<strong>on</strong>structi<strong>on</strong><br />
materials c<strong>on</strong>taminated by fissi<strong>on</strong>, corrosi<strong>on</strong> and transuranic radi<strong>on</strong>uclides remains <strong>on</strong>e of the most urgent and<br />
complicated ecological problems. Am<strong>on</strong>g the existing methods having different efficiencies in regard to such materials<br />
dec<strong>on</strong>taminati<strong>on</strong>, applicati<strong>on</strong> of selective sorbents put into a humid medium to be dec<strong>on</strong>taminated (ground, bulk<br />
materials) appears to be rather extensive. However, the efficiency of such an approach is significantly limited by<br />
difficulties c<strong>on</strong>cerned with uniform sorbent distributi<strong>on</strong> in porous media and completeness of spent sorbents removal for<br />
final disposal. In this paper we suggest a principally new approach to preparati<strong>on</strong> of colloid-stable selective sorbents for<br />
cesium uptake using immobilizati<strong>on</strong> of transiti<strong>on</strong> metals (cobalt, nickel, and copper) ferrocyanides in nanosized<br />
carboxylic latex emulsi<strong>on</strong>s. <str<strong>on</strong>g>The</str<strong>on</strong>g> effects of ferrocyanide compositi<strong>on</strong>, pH, and media salinity <strong>on</strong> the sorpti<strong>on</strong> properties of<br />
the colloid-stable sorbents toward cesium i<strong>on</strong>s were studied in soluti<strong>on</strong>s c<strong>on</strong>taining up to 200 g/l sodium nitrate or<br />
potassium chloride. <str<strong>on</strong>g>The</str<strong>on</strong>g> sorpti<strong>on</strong> capacities of the colloid sorbents based <strong>on</strong> mixed potassium/transiti<strong>on</strong> metals<br />
ferrocyanides were in the range 1.45-1.86 mol Cs/mol ferrocyanide with the highest value found for the copper<br />
ferrocyanide. It was shown that the obtained colloid-stable sorbents were capable to penetrate through bulk materials<br />
without filtrati<strong>on</strong> that makes them applicable for dec<strong>on</strong>taminati<strong>on</strong> of solids, e.g. soils, zeolites, spent i<strong>on</strong>-exchange resins<br />
c<strong>on</strong>taminated with cesium radi<strong>on</strong>uclides. After dec<strong>on</strong>taminati<strong>on</strong> of liquid or solid radioactive wastes the colloid-stable<br />
sorbents can be easily separated from soluti<strong>on</strong>s by precipitati<strong>on</strong> with cati<strong>on</strong>ic flocculants providing localizati<strong>on</strong> of<br />
radi<strong>on</strong>uclides in a small volume of the precipitates formed. Besides, functi<strong>on</strong>alized latex particles can be used for<br />
preparati<strong>on</strong> of carb<strong>on</strong> fiber/ferrocyanide composite materials for cesium uptake using electrodepositi<strong>on</strong> method.<br />
Applicati<strong>on</strong> of the carb<strong>on</strong> fibers as an inert support for ferrocyanides, in general, significantly improves the sorpti<strong>on</strong><br />
kinetics, but washing out of ferrocyanide fines from the fiber surface limits the potential of such materials. When<br />
ferrocyanides are deposited in a form of nanocrystals stabilized by latexes which undergo electropolymerizati<strong>on</strong> <strong>on</strong> the<br />
fiber surface, the thin polymeric film formed substantially improves the stability of the composite and prevents loss of<br />
ferrocyanide during sorbent applicati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> effect of electrodepositi<strong>on</strong> c<strong>on</strong>diti<strong>on</strong>s <strong>on</strong> composite morphology,<br />
ferrocyanide loading and cesium distributi<strong>on</strong> coefficient in media with different salinity has been discussed.<br />
SESSION H11: SF/TRU/HLW Poster<br />
1) 40001 – Investigati<strong>on</strong> of Colloid-facilitated Effects <strong>on</strong> the Radi<strong>on</strong>uclides Migrati<strong>on</strong> in the Fractured Rock with<br />
a Kinetic Solubility-Limited Dissoluti<strong>on</strong> Model<br />
Chun-Ping Jen,Nati<strong>on</strong> Chung Cheng University (Taiwan);<br />
Neng-Chuan Tien, Energy and Envir<strong>on</strong>ment Research Laboratories,<br />
Industrial Technology Research Institute (Taiwan)<br />
Nuclides can move with the groundwater either as solutes or colloids, where the latter mechanism generally results<br />
in much shorter traveling time as they interact str<strong>on</strong>gly with solid phases, such as actinides. It is therefore essential to<br />
assess the relative importance of these two transport mechanisms for different nuclides. <str<strong>on</strong>g>The</str<strong>on</strong>g> relative importance of<br />
colloids depends <strong>on</strong> the nature and c<strong>on</strong>centrati<strong>on</strong> of colloids in groundwater. Plut<strong>on</strong>ium (Pu), neptunium (Np), uranium<br />
(U) and americium (Am) are four nuclides of c<strong>on</strong>cern for l<strong>on</strong>g-term emplacement of nuclear wastes at potential<br />
repository sites. If attached to ir<strong>on</strong> oxide, clay or silica colloids in groundwater. Str<strong>on</strong>g sorpti<strong>on</strong> of the actinides by<br />
colloids in groundwater may facilitate transport of these nuclides al<strong>on</strong>g potential flow paths. Solubility-limited<br />
dissoluti<strong>on</strong> model models can be used to determine the release of the safety assessment for nuclear waste in geological<br />
disposal sites. <str<strong>on</strong>g>The</str<strong>on</strong>g> present study investigates the effect of colloid <strong>on</strong> the transport of solubility limited nuclide under the<br />
101
Abstracts<br />
kinetic solubility limited dissoluti<strong>on</strong> (KSLD) boundary c<strong>on</strong>diti<strong>on</strong> in fractured media. <str<strong>on</strong>g>The</str<strong>on</strong>g> release rate of nuclide would<br />
proporti<strong>on</strong>al to the difference between the saturati<strong>on</strong> c<strong>on</strong>centrati<strong>on</strong> and the inlet aqueous c<strong>on</strong>centrati<strong>on</strong> of nuclide. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
presence of colloids could decrease the aqueous c<strong>on</strong>centrati<strong>on</strong> of nuclide and thus could increase the release flux of<br />
nuclide from the waste form.<br />
2) 40013 – Modeling hydraulic c<strong>on</strong>ductivity and swelling pressure of several kinds of bent<strong>on</strong>ites affected by<br />
salinity of water<br />
Yukihisa Tanaka, Takuma Hasegawa, Kunihiko Nakamura, CRIEPI (Japan)<br />
In case of c<strong>on</strong>structi<strong>on</strong> of repository for radioactive waste near the coastal area, the effect of salinity of water <strong>on</strong><br />
hydraulic c<strong>on</strong>ductivity as well as swelling pressure of bent<strong>on</strong>ite as an engineered barrier should be c<strong>on</strong>sidered because it<br />
is known that the hydraulic c<strong>on</strong>ductivity of bent<strong>on</strong>ite increases and swelling pressure decreases with increasing in salinity<br />
of water. Though the effect of salinity of water <strong>on</strong> hydraulic c<strong>on</strong>ductivity and swelling pressure of bent<strong>on</strong>ite has been<br />
investigated experimentally, it is necessary to elucidate and to model the mechanism of the phenomen<strong>on</strong> because various<br />
kinds of bent<strong>on</strong>ites may possibly be placed in various salinity of ground water. Thus, in this study, a model for evaluating<br />
hydraulic c<strong>on</strong>ductivity as well as swelling pressure of compacted bent<strong>on</strong>ite is proposed c<strong>on</strong>sidering the effect of salinity<br />
of water as follows :<br />
a) Change in number of flakes of a stack of m<strong>on</strong>tmorill<strong>on</strong>ite because of cohesi<strong>on</strong><br />
b) Change in viscosity of water in interlayer between flakes of m<strong>on</strong>tmorill<strong>on</strong>ite.<br />
Quantitative evaluati<strong>on</strong> method for hydraulic c<strong>on</strong>ductivity and swelling characteristics of several kinds of bent<strong>on</strong>ite<br />
under saline water is proposed based <strong>on</strong> the model menti<strong>on</strong>ed above.<br />
3) 40018 – Current R & D activities of the study <strong>on</strong> l<strong>on</strong>g-term stability of geological envir<strong>on</strong>ments<br />
Takahiro Hanamuro, Kenichi Yasue, Yoko Saito-Kokubu,Koichi Asamori,<br />
Tsuneari Ishimaru, Koji Umeda, JAEA (Japan)<br />
Japanese islands are located in a tect<strong>on</strong>ically active z<strong>on</strong>e, where earthquakes and volcanic erupti<strong>on</strong>s frequently<br />
occur. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore the understanding of the l<strong>on</strong>g-term stability of geological envir<strong>on</strong>ment is required for assessing the<br />
l<strong>on</strong>g-term behaviour of the geological disposal system of high level radioactive waste (HLW) in Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> Japan<br />
Atomic Energy Agency (JAEA) is promoting the establishment of investigati<strong>on</strong> and assessment methods of the l<strong>on</strong>g-term<br />
stability of geological envir<strong>on</strong>ment necessary for site selecti<strong>on</strong> and safety assessment of HLW geological disposal.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Nuclear Waste Management Organizati<strong>on</strong> of Japan (NUMO) is the implementati<strong>on</strong> body of HLW disposal in<br />
Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> preliminary investigati<strong>on</strong> areas for HLW disposal site, selected by NUMO in the future, are supposed to be<br />
selected excluding the z<strong>on</strong>es affected by already-known active faults identified by nati<strong>on</strong>wide and site-specific literature<br />
surveys. <str<strong>on</strong>g>The</str<strong>on</strong>g>y are also supposed to be selected with excluding the area within 15 km radius of the center of a Quaternary<br />
volcano and the z<strong>on</strong>es affected by thermal and hydrothermal activities identified by site-specific literature surveys. For<br />
uplift, denudati<strong>on</strong> and climatic/sea-level changes, it is necessary that the change of geological envir<strong>on</strong>ment caused by<br />
uplift/denudati<strong>on</strong> and climatic/sea-level changes is assessed for HLW geological disposal system.<br />
For seismicity and faulting, some detecti<strong>on</strong> techniques for active faults with no surface expressi<strong>on</strong>, by using helium<br />
isotope ratio of hot spring gas or detecti<strong>on</strong> of hydrogen gas, and studying <strong>on</strong> the assessment of fault activities are<br />
developed. For volcanism and geothermal activity, heat source of geothermal anomaly area in the n<strong>on</strong>-volcanic regi<strong>on</strong> are<br />
c<strong>on</strong>sidered and some detecti<strong>on</strong> techniques for high-temperature fluid and magma at deep underground, by using seismic<br />
tomography, magnetotelluric method and helium isotope ratio of hot spring gas, are c<strong>on</strong>structed. For uplift, denudati<strong>on</strong><br />
and climatic/sea-level changes, a methodology to understand future topographic change with time is developed. Also, for<br />
dating techniques as an essential part to proceed <strong>on</strong> these studies, C-14 dating by using AMS and (U-Th)/He dating by<br />
using QMS and ICP-MS have developed, and Be-10 dating by using AMS has been being developed.<br />
We are planning the establishment of assessment methods for l<strong>on</strong>g-term stability of geological envir<strong>on</strong>ment;<br />
assessment of activities of faults encountered by underground excavati<strong>on</strong>, development of l<strong>on</strong>g-term estimati<strong>on</strong> methods<br />
of volcanisms and hydrothermal activities, and hydrogeological analyses c<strong>on</strong>sidering topographic change in the future.<br />
4) 40019 – In Situ Stress Measurements in Siliceous Mudst<strong>on</strong>es at Hor<strong>on</strong>obe Underground Research Laboratory,<br />
Japan<br />
Hiroyuki Sanada, Takahiro Nakamura, Yutaka Sugita, JAEA (Japan)<br />
As part of the research and development program <strong>on</strong> the HLW geological disposal, JAEA has been implementing<br />
the Hor<strong>on</strong>obe Underground Research Laboratory (URL) Project investigating sedimentary rock formati<strong>on</strong>s distributed in<br />
Hor<strong>on</strong>obe area, Hokkaido, Japan. To optimize the design and c<strong>on</strong>structi<strong>on</strong> of underground excavati<strong>on</strong>s for any HLW<br />
repository, a thorough evaluati<strong>on</strong> of initial stress c<strong>on</strong>diti<strong>on</strong> will be required. Studies of initial stress c<strong>on</strong>diti<strong>on</strong>s in<br />
sedimentary rock aren't enough, since important underground structures such as those for underground power plants and<br />
caverns for storage of liquefied petroleum or natural gas in Japan have mainly been c<strong>on</strong>structed in hard rock.<br />
Additi<strong>on</strong>ally, initial stress measurements in sedimentary rocks are inherently more difficult compared to hard rock. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
authors have been implementing the research and development program at Hor<strong>on</strong>obe to clarify the in situ stress<br />
102
Abstracts<br />
c<strong>on</strong>diti<strong>on</strong>s in siliceous mudst<strong>on</strong>es at the URL. <str<strong>on</strong>g>The</str<strong>on</strong>g> objective of this work is to establish a strategy for an in situ stress<br />
measurement program for geological disposal and to develop an understanding of the in situ stress c<strong>on</strong>diti<strong>on</strong>s in the deep<br />
underground formed by the sedimentary rocks. <str<strong>on</strong>g>The</str<strong>on</strong>g> applicati<strong>on</strong> of several stress measurement methods to the Hor<strong>on</strong>obe<br />
siliceous mudst<strong>on</strong>es carried out during the surface-based investigati<strong>on</strong>s and the investigati<strong>on</strong>s during c<strong>on</strong>structi<strong>on</strong> of the<br />
underground facilities, as well as informati<strong>on</strong> <strong>on</strong> the initial stress state around the Hor<strong>on</strong>obe URL are described in this<br />
paper. During the surface-based investigati<strong>on</strong>s, determinati<strong>on</strong> of deep in situ stress was d<strong>on</strong>e using hydraulic fracturing<br />
(HF), borehole breakout informati<strong>on</strong> in deep boreholes and core-based methods such as AE and DSCA. Subsurface<br />
investigati<strong>on</strong>s during c<strong>on</strong>structi<strong>on</strong> of the underground facilities utilized, the Compact C<strong>on</strong>ical Ended Borehole<br />
Overcoring (CCBO) method and hydraulic testing of pre-existing fractures (HTPF) were c<strong>on</strong>ducted in order to validate<br />
results from initial stress measurements in the surface-based investigati<strong>on</strong>s. HF results indicate that horiz<strong>on</strong>tal maximum<br />
and minimum principal stresses increase linearly with depth. <str<strong>on</strong>g>The</str<strong>on</strong>g> minimum principal stress is almost equivalent to<br />
overburden pressure. <str<strong>on</strong>g>The</str<strong>on</strong>g> maximum principal stress estimated from the HF and borehole breakout data is almost E-W.<br />
This is similar to the tect<strong>on</strong>ic movement directi<strong>on</strong> in the vicinity of the Hor<strong>on</strong>obe URL. Due to tect<strong>on</strong>ic movement,<br />
horiz<strong>on</strong>tal maximum stress is almost 1.5 times larger than the horiz<strong>on</strong>tal minimum stress. Vertical stress determined from<br />
HTPF during c<strong>on</strong>structi<strong>on</strong> of the underground facilities is almost equal to the overburden pressure.<br />
5) 40038 – Low alkaline Cement Used in the C<strong>on</strong>structi<strong>on</strong> of a Gallery in the Hor<strong>on</strong>obe Underground Research<br />
Laboratory<br />
Masashi Nakayama, Haruo Sato, Yutaka Sugita, Seiji ITO, JAEA (Japan);<br />
Masashi Minamide, Yoshito Kitagawa, Taisei Cooperati<strong>on</strong> (Japan)<br />
In Japan, any high level radioactive waste repository is to be c<strong>on</strong>structed at over 300m depth below surface. Tunnel<br />
support is used for safety during the c<strong>on</strong>structi<strong>on</strong> and operati<strong>on</strong>, and shotcrete and c<strong>on</strong>crete lining are used as the tunnel<br />
support. C<strong>on</strong>crete is a composite material comprised of aggregate, cement and various additives. Low alkaline cement<br />
has been developed for the l<strong>on</strong>g term stability of the barrier systems whose performance could be negatively affected by<br />
highly alkaline c<strong>on</strong>diti<strong>on</strong>s arising due to cement used in a repository. Japan Atomic Energy Agency (JAEA) has<br />
developed a low alkaline cement, named as HFSC (High fly-ash silicafume cement), c<strong>on</strong>taining over 60wt% of<br />
silica-fume (SF) and coal ash (FA). JAEA are presently c<strong>on</strong>structing an underground research laboratory (URL) at<br />
Hor<strong>on</strong>obe for research and development in the geosciences and repository engineering technology. HFSC was used<br />
experimentally as the shotcrete material in c<strong>on</strong>structi<strong>on</strong> of part of the 140m deep gallery in Hor<strong>on</strong>obe URL. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
objective of this experiment was to assess the performance of HFSC shotcrete in terms of mechanics, workability,<br />
durability, and so <strong>on</strong>. HFSC used in this experiment is composed of 40wt% OPC (Ordinary Portland Cement), 20wt% SF,<br />
and 40wt% FA. This compositi<strong>on</strong> was determined based <strong>on</strong> mechanical testing of various mixes of the above<br />
comp<strong>on</strong>ents. Because of the low OPC c<strong>on</strong>tent, the strength of HFSC tends to be lower than that of OPC in normal<br />
c<strong>on</strong>crete. <str<strong>on</strong>g>The</str<strong>on</strong>g> total length of tunnel using HFSC shotcrete is about 73m and about 500m3 of HFSC was used. This<br />
experimental c<strong>on</strong>structi<strong>on</strong> c<strong>on</strong>firmed the workability of HFSC shotcrete. Although several in-situ experiments using low<br />
alkaline cement as shotcrete have been performed at a small scale, this applicati<strong>on</strong> of HFSC at the Hor<strong>on</strong>obe URL is the<br />
first full scale applicati<strong>on</strong> of low alkaline cement in the c<strong>on</strong>structi<strong>on</strong> of a URL in the world. In the paper, we present<br />
detailed results of the in-situ c<strong>on</strong>structi<strong>on</strong> test and the future works.<br />
6) 40040 – Effects of Nitrate <strong>on</strong> Nuclide Solubility for Co-locati<strong>on</strong> Disposal of TRU Waste and HLW<br />
Gento Kamei, Morihiro Mihara, JAEA (Japan); Toshiyuki Nakazawa,<br />
Norikazu Yamada, Mitsubishi Materials Corp. (Japan)<br />
TRU wastes are generated by reprocessing spent fuel from nuclear power plants and by fabricating MOX fuel in<br />
Japan. Some of the TRU wastes are expected to be disposed of deep underground to isolate it from the biosphere in the<br />
l<strong>on</strong>g-term. To optimize the disposal of TRU waste, a co-locati<strong>on</strong> disposal with high level waste, HLW, is being<br />
c<strong>on</strong>sidered. A part of TRU waste includes a large amount of nitrate salt, the effects of which have to be evaluated in a<br />
safety assessment of co-locati<strong>on</strong> disposal.<br />
Solubility is <strong>on</strong>e of the important parameters for the safety assessment of HLW disposal. Large c<strong>on</strong>centrati<strong>on</strong>s of<br />
nitrate i<strong>on</strong>s from TRU waste might affect the oxidati<strong>on</strong> state and c<strong>on</strong>sequently the solubility of different radi<strong>on</strong>uclides in<br />
the HLW waste. In additi<strong>on</strong>, it is necessary to c<strong>on</strong>sider complex formati<strong>on</strong> of nitrate i<strong>on</strong>s with radi<strong>on</strong>uclides, as well as<br />
the formati<strong>on</strong> of amm<strong>on</strong>ia by microbes and/or by reacti<strong>on</strong>s with reducing materials in the disposal facility. C<strong>on</strong>sequently,<br />
complex formati<strong>on</strong> of amm<strong>on</strong>ia with radi<strong>on</strong>uclides must also be evaluated.<br />
In the current study, the effects of nitrate salt <strong>on</strong> radi<strong>on</strong>uclide solubility were investigated experimentally with<br />
c<strong>on</strong>siderati<strong>on</strong> given to the above perturbati<strong>on</strong>s. Solubility experiments of important and redox sensitive radi<strong>on</strong>uclides,<br />
Tc(IV), Np(IV) and Se(0), were performed using various c<strong>on</strong>centrati<strong>on</strong>s of sodium nitrate (NaNO3) and of Np(V) in<br />
NaNO3 soluti<strong>on</strong>s to investigate complex formati<strong>on</strong> with NO3- i<strong>on</strong>s. Solubility experiments of Pd(II), Sn(IV) and Nb(V)<br />
using amm<strong>on</strong>ium chloride (NH4Cl) soluti<strong>on</strong> were also undertaken to investigate complex formati<strong>on</strong> with NH3/NH4+<br />
i<strong>on</strong>s. A chemical equilibrium model was applied to assist the interpretati<strong>on</strong> of the experimental results. No significant<br />
solubility enhancement was observed for Np and Se due to oxidati<strong>on</strong> by nitrate i<strong>on</strong>s. Tc solubility was, however,<br />
increased by <strong>on</strong>e order of magnitude under high nitrate c<strong>on</strong>centrati<strong>on</strong>s. Solubility enhancement by complex formati<strong>on</strong> of<br />
nitrate i<strong>on</strong>s with Np(V) was not observed. Solubility enhancement by complex formati<strong>on</strong> of Sn and Nb were not also<br />
observed, <strong>on</strong>ly Pd solubility was increased by complex formati<strong>on</strong> with NH3/NH4+ i<strong>on</strong>s. Tendencies of the enhancement<br />
103
Abstracts<br />
of Pd solubility were explained by the chemical equilibrium model.<br />
This work was funded by ANRE: Agency for Natural Resources and Energy, of METI: Ministry of Ec<strong>on</strong>omy, Trade<br />
and Industry, of Japan.<br />
7) 40047 – A study <strong>on</strong> groundwater infiltrati<strong>on</strong> in the Hor<strong>on</strong>obe area, northern Hokkaido, Japan<br />
Hideharu Yokota, Yamamoto Yoichi, Keisuke Maekawa, Minoru Hara, JAEA (Japan)<br />
It is important for assessing the safety of geological disposal of high-level radioactive waste to understand<br />
groundwater flow as the driving force of mass transport. In the groundwater-flow simulati<strong>on</strong>, hydraulic boundary<br />
c<strong>on</strong>diti<strong>on</strong>s are required, including groundwater-recharge rates. In the Hor<strong>on</strong>obe area of northern Hokkaido, the Japan<br />
Atomic Energy Agency (JAEA) has been carrying out the Hor<strong>on</strong>obe Underground Research Laboratory (URL) Project to<br />
understand characteristics of the geological envir<strong>on</strong>ment. To obtain various hydrological data to estimate the recharge<br />
rate by water balance, meteorological observati<strong>on</strong> and observati<strong>on</strong> of river flux, etc. in the Hor<strong>on</strong>obe area (snowy cold<br />
regi<strong>on</strong>) have been carried out. However, infiltrati<strong>on</strong> of water from the surface is difficult to clarify in detail because water<br />
near ground surface is sensitive to external influence such as climatic variati<strong>on</strong>s. It is important for precise evaluati<strong>on</strong> of<br />
groundwater flow to understand shallow groundwater-flow systems (ground surface to tens of meters at depth) as a part<br />
of hydraulic boundary c<strong>on</strong>diti<strong>on</strong>s. In the Hor<strong>on</strong>obe area, subsurface temperature and soil moisture c<strong>on</strong>tent have been<br />
observed at the URL (GL-0.7m to GL-2.3m) site since 2005 and at Hokushin Meteorological Stati<strong>on</strong> (HMS, GL-0.1m to<br />
GL-1.1m) since 2008. As results of these observati<strong>on</strong>s, it is clear that similar processes operate at both sites. Subsurface<br />
temperatures become lower with depth in the summer and higher with depth in the winter. <str<strong>on</strong>g>The</str<strong>on</strong>g> lowest subsurface<br />
temperatures at the shallowest and deepest at depth are observed in the middle of April and early May respectively.<br />
C<strong>on</strong>currently, soil moisture c<strong>on</strong>tent increases rapidly. In additi<strong>on</strong>, the observed data also show that the subsurface<br />
temperature is higher than 0°C throughout the year, and keeps decreasing until early May (snow-melting seas<strong>on</strong>). From<br />
these results, it is suggested that, regardless of the air temperature, water at 0°C is supplied from the bottom of<br />
snow-cover to ground surface by bottom snow melting due to the insulating effect of snow. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, the subsurface<br />
temperature firstly becomes the lowest at the shallowest depth. Subsequently, subsurface temperatures at greater depths<br />
decrease as the cold water infiltrates to depth with time. For the estimati<strong>on</strong> of boundary c<strong>on</strong>diti<strong>on</strong>s in groundwater-flow<br />
simulati<strong>on</strong>, in this study, the shallow groundwater-flow system has been examined qualitatively <strong>on</strong> the basis of the<br />
seas<strong>on</strong>al variati<strong>on</strong> of the groundwater infiltrati<strong>on</strong>. Results have revealed the groundwater recharge occurring in a<br />
snow-covered regi<strong>on</strong>. In the future, it is planed that quantitative assessments will be made by the observed data of the<br />
weighing lysimeter.<br />
8) 40051 – Effective Use of Uranium Resources and Dissoluti<strong>on</strong> of Recovery Uranium Storage Accumulati<strong>on</strong> by a<br />
Uranium Multi-recycle System<br />
Yuzo Yamashita, Yuzo Yamashita, Takeshi Nakamura, Kyushu University (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> uranium recovered from LWR spent fuels, c<strong>on</strong>taining an amount of U-235 comparable to that in the natural<br />
uranium, can be recycled as uranium fuels for LWRs by re-enrichment using a c<strong>on</strong>venti<strong>on</strong>al centrifuge cascade. However,<br />
the remade fuel is inferior to the original fuel produced from the natural uranium <strong>on</strong> the burn-up performance, because<br />
the former includes U-236 as neutr<strong>on</strong> absorber which is yielded in the spent fuel and then enhanced in re-enrichment<br />
process. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, a few times recycle of recovered uranium may be available but its successive multi-recycle is not<br />
recommendable because of successive decline in burn-up resulting from U-236 accumulating in remade fuels. In this<br />
study, an idea of uranium fuel recycling is proposed which is of the feed-back of recovered uranium to a natural uranium<br />
enriching cascade. Since this cascade processes a mixture of natural and recovered uranium, the product c<strong>on</strong>tains U-236<br />
enriched but diluted with the U-236-free bulk of natural uranium. In this process, the c<strong>on</strong>centrati<strong>on</strong> of U-236 in the fuels<br />
reaches a balance with increase in recycle times. <str<strong>on</strong>g>The</str<strong>on</strong>g> multi-recycling fuels perform the burn-up degrees in PWRs<br />
declining but comparing favorably with c<strong>on</strong>veti<strong>on</strong>al uranium <strong>on</strong>es. <str<strong>on</strong>g>The</str<strong>on</strong>g> multi-recycling system not <strong>on</strong>ly makes effective<br />
use of nuclear fuel resources, but also dissolves the problem of accumulating inventory in the storage of recovered<br />
uranium taking the major volume of spent fuels.<br />
9) 40053 – Advanced ORIENT Cycle - Progress <strong>on</strong> Fissi<strong>on</strong> Product Separati<strong>on</strong> and Utilizati<strong>on</strong><br />
Isao Yamagishi, Masaki Ozawa, JAEA (Japan); Hitoshi Mimura, Tohoku Univ.(Japan);<br />
Shohei Kanamura, Koji Mizuguchi, Toshiba Corporati<strong>on</strong> (Japan)<br />
Fissi<strong>on</strong> reacti<strong>on</strong> of U-235 generates more than 40 elements and 400 nuclides in the spent fuel. Am<strong>on</strong>g them, 31<br />
elements are categorized as rare metals. Typical yields of Pd, Ru, Rh (PGM) and Tc as rare metals will reach around<br />
11kg, 13kg, 4kg and 3kg, respectively per metric t<strong>on</strong> of the reference FBR spent fuel (150GWd/t, cooled 5 years). Based<br />
<strong>on</strong> a ground swell <strong>on</strong> enhancements of minimizati<strong>on</strong> of radio-ecological impacts and ec<strong>on</strong>omical expenditures, nuclear<br />
fuel cycle c<strong>on</strong>cept itself is required to be changed. Adv.-ORIENT (Advanced Optimizati<strong>on</strong> by Recycling Instructive<br />
Elements) Cycle strategy was hence drawn up for the minimizati<strong>on</strong> of radioactive waste and utilizati<strong>on</strong> of<br />
elements/nuclides in the wastes simultaneously., and has been developed at Japan Atomic Energy Agency. <str<strong>on</strong>g>The</str<strong>on</strong>g> present<br />
paper deals with the separati<strong>on</strong> process of fissi<strong>on</strong> products in the Adv.-ORIENT Cycle, which c<strong>on</strong>sists of the<br />
104
Abstracts<br />
chromatographic separati<strong>on</strong> of heat-generating Cs and Sr, and the electrodepositi<strong>on</strong> of Pd, Ru, Rh and Tc. Highly<br />
functi<strong>on</strong>al inorganic adsorbent (silica gel loaded with amm<strong>on</strong>ium molybdophosphate, AMP-SG) and organic<br />
microcapsule (alginate (ALG) gel polymer enclosed with crown ether D18C6) were investigated for separati<strong>on</strong> of Cs and<br />
Sr, respectively, from high-level liquid waste (HLLW). <str<strong>on</strong>g>The</str<strong>on</strong>g> AMP-SG adosorbed more than 99% of Cs from the<br />
simulated HLLW selectively. <str<strong>on</strong>g>The</str<strong>on</strong>g> ALG microcapsule adsorbed 0.0249 mmol/g of Sr and exhibited the order of its<br />
selectivity: Ba > Sr > Pd >> Ru > Rb > Ag. Separated Cs and Sr will be immobilized in ceramic forms using zeolites for<br />
the utilizati<strong>on</strong> as heat and/or radiati<strong>on</strong> source. <str<strong>on</strong>g>The</str<strong>on</strong>g> electrodepositi<strong>on</strong> is advantageous for both recovery and utilizati<strong>on</strong> of<br />
PGM and Tc because these elements are recovered as metal (Ru, Rh, Pd, (Tc)) and/or oxide (Tc) form <strong>on</strong> a Pt electrode.<br />
In the presence of Pd or Rh the reducti<strong>on</strong> of Ru and Tc was accelerated in hydrochloric acid media. This co-depositi<strong>on</strong><br />
effect, however, was less in nitric acid. In the simulated HLLW, the redox reacti<strong>on</strong> of Fe(III)/Fe(II) disturbed depositi<strong>on</strong><br />
of elements except for Pd. <str<strong>on</strong>g>The</str<strong>on</strong>g> deposits <strong>on</strong> Pt electrode showed higher catalytic reactivity <strong>on</strong> electrolytic hydrogen<br />
producti<strong>on</strong> than the original Pt electrode.<br />
Keywords; Nuclear waste, Separati<strong>on</strong>, Utilizati<strong>on</strong>, Adsorpti<strong>on</strong>, electrolysis, Cesium, Str<strong>on</strong>tium, Ruthenium,<br />
Rhodium, Palladium, Technetium, PGM<br />
10) 40064 – Hydrogeological Characterizati<strong>on</strong> based <strong>on</strong> L<strong>on</strong>g Term Groundwater Pressure M<strong>on</strong>itoring<br />
Shuji Daimaru, Ryuji Takeuchi, Masaki Takeda, Masayuki Ishibashi, JAEA (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Mizunami Underground Research Laboratory (MIU) is now under c<strong>on</strong>structi<strong>on</strong> by the Japan Atomic Energy<br />
Agency in the T<strong>on</strong>o area of central Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> MIU project is being implemented in three overlapping Phases:<br />
Surface-based Investigati<strong>on</strong> (Phase I), C<strong>on</strong>structi<strong>on</strong> (Phase II) and Operati<strong>on</strong> (Phase III). <str<strong>on</strong>g>The</str<strong>on</strong>g> changes of groundwater<br />
pressure due to shaft excavati<strong>on</strong> can be c<strong>on</strong>sidered analogous to a large-scale pumping test. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, there is the<br />
possibility that the site scale groundwater field (several km square) can be approximated by the l<strong>on</strong>g-term groundwater<br />
pressure m<strong>on</strong>itoring data from Phase II. Based <strong>on</strong> the m<strong>on</strong>itoring observati<strong>on</strong>s, hydrogeological characteristics were<br />
estimated using the s–log(t/r^2) plot based <strong>on</strong> the Cooper-Jacob straight line method. Results of the s-log(t/r^2) plots are<br />
as follows. <str<strong>on</strong>g>The</str<strong>on</strong>g> groundwater flow field around the MIU c<strong>on</strong>structi<strong>on</strong> site is separated into domains by an impermeable<br />
fault. In other words, the fault is a hydraulic barrier. Hydraulic c<strong>on</strong>ductivity calculated from s-log(t/r^2) plots are in the<br />
order of 1.0E-7(m/s). <str<strong>on</strong>g>The</str<strong>on</strong>g> above results from the l<strong>on</strong>g term m<strong>on</strong>itoring during PhaseII are a verificati<strong>on</strong> of the<br />
hydrogeological characteristics determined in the Phase I investigati<strong>on</strong>s. Keywords: Large scale pumping test, l<strong>on</strong>g term<br />
pressure m<strong>on</strong>itoring, shaft excavati<strong>on</strong>, s-log(t/r^2) plot, hydrogeological characteristics.<br />
11) 40065 – Development Of <str<strong>on</strong>g>The</str<strong>on</strong>g> Quality Management System For Borehole Investigati<strong>on</strong>s: (2) Quality<br />
Management Systems For Hydrochemical Investigati<strong>on</strong>s,<br />
Takanori Kunimaru, Kunio Ota, Kenji Amano, JAEA (Japan);<br />
W Russell Alexander, Bedrock Geosciences (Switzerland)<br />
An appropriate Quality Management System (QMS), which is am<strong>on</strong>g the first tools required for repository site<br />
characterisati<strong>on</strong>, will save <strong>on</strong> effort by reducing errors and the requirement to resample and reanalyse – but this can <strong>on</strong>ly<br />
be guaranteed by c<strong>on</strong>tinuously assessing if the system is truly fit-for-purpose and amending it as necessary based <strong>on</strong> the<br />
practical experience of the end-users <strong>on</strong>-site. As part of the nati<strong>on</strong>al research and development programme for deep<br />
geological disposal of radioactive waste, the Japan Atomic Energy Agency has established two Underground Research<br />
Laboratories (URL) based around Hor<strong>on</strong>obe, northern Japan, and Mizunami, central Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> main aim of the URL<br />
programme is to define comprehensive techniques for future repository site characterisati<strong>on</strong>. At the Hor<strong>on</strong>obe URL,<br />
investigati<strong>on</strong> of the geological envir<strong>on</strong>ment within sedimentary host formati<strong>on</strong>s is currently <strong>on</strong>going and <strong>on</strong>e facet of this<br />
is <strong>on</strong>e of the few examples worldwide (and the first use in Japan) of the study of rock matrix porewater hydrochemistry,<br />
in c<strong>on</strong>juncti<strong>on</strong> with groundwater hydrochemistry. <str<strong>on</strong>g>The</str<strong>on</strong>g> data and interpretati<strong>on</strong> are described in detail elsewhere but,<br />
before detailed data interpretati<strong>on</strong>, the first priority should always be an analysis of the data quality and this is addressed<br />
here. <str<strong>on</strong>g>The</str<strong>on</strong>g> quality of the porewater data have been categorised based <strong>on</strong> an existing system of ranking groundwater data<br />
quality, which has been developed for the fractured crystalline rocks of the Fennoscandian Shield. <str<strong>on</strong>g>The</str<strong>on</strong>g> ranks range from<br />
Category 1 (highest quality) to Category 5 (lowest quality) and of particular importance in the categorisati<strong>on</strong> criteria are<br />
(i) the degree of porewater c<strong>on</strong>taminati<strong>on</strong> with drilling fluid, (ii) indicati<strong>on</strong>s of sample perturbati<strong>on</strong>s such as oxidati<strong>on</strong> or<br />
CO2 reacti<strong>on</strong> and (iii) the completeness of major i<strong>on</strong> and isotope analytical data. With the integrati<strong>on</strong> of all available<br />
informati<strong>on</strong> <strong>on</strong> hydrochemistry, hydrogeology and borehole history, more than 150 porewater and 24 groundwater<br />
datasets have been examined to date. <str<strong>on</strong>g>The</str<strong>on</strong>g> results of the QA audit by multi-operators have been compared in order to<br />
assess the objectivity of the categorisati<strong>on</strong>, methodology and this clearly shows operator-dependent differences in<br />
categorisati<strong>on</strong> of the same data set. As such, the initial guidelines for assigning the QA categories have been improved so<br />
as to reduce dependence <strong>on</strong> expert judgement and this approach will be discussed in detail here. This approach will<br />
increase transparency in the data handling and so increase stakeholders’ c<strong>on</strong>fidence in both the data set itself and in the<br />
results obtained using such data for a repository site characterisati<strong>on</strong>.<br />
105
Abstracts<br />
12) 40067 – An Analytical Model <strong>on</strong> the Sealing Performance of Space for the Design of Buffer Material and<br />
Backfill Material<br />
Haruo Sato, JAEA (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> self-sealing functi<strong>on</strong> of spaces between buffer material and overpack, tunnel wall and disposal pit by swelling<br />
occurred with water penetrati<strong>on</strong> is expected for bent<strong>on</strong>ite which will be used as buffer material and part of the backfill<br />
material in the geological of high-level radioactive waste in Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> clearance filling properties of Na-bent<strong>on</strong>ite for<br />
buffer material and backfill material specificati<strong>on</strong>s have been studied for distilled water and saline water c<strong>on</strong>diti<strong>on</strong>s, for<br />
example, it is reported that Na-bent<strong>on</strong>ite seals clearance even under saline water c<strong>on</strong>diti<strong>on</strong>s in a range of effective<br />
bent<strong>on</strong>ite densities which are higher than 1.3 kg/dm3, for a bent<strong>on</strong>ite dry density of 1.8 kg/dm3 and a clearance ratio<br />
(volumetric ratio of clearance volume to total volume including pore and the clearance) of 10 % (1.11 in volumetric<br />
swelling ratio: Rvs) in experiments for Kunigel-V1 (Na-m<strong>on</strong>tmorill<strong>on</strong>ite c<strong>on</strong>tent ca. 50 wt.%). Although such<br />
informati<strong>on</strong> is useful for judging whether clearance is filled, the filling properties of bent<strong>on</strong>ite depend <strong>on</strong> groundwater<br />
c<strong>on</strong>diti<strong>on</strong>, silica sand c<strong>on</strong>tent, m<strong>on</strong>tmorill<strong>on</strong>ite c<strong>on</strong>tent in the bent<strong>on</strong>ite and the bent<strong>on</strong>ite dry density, even though at the<br />
same effective bent<strong>on</strong>ite density. In the present study, the author c<strong>on</strong>structed an analytical model <strong>on</strong> the clearance filling<br />
performance for the design of buffer material and backfill material, based <strong>on</strong> the swelling properties of<br />
Na-m<strong>on</strong>tmorill<strong>on</strong>ite which is the clay mineral c<strong>on</strong>stituent of bent<strong>on</strong>ite. In the modelling, experimental data <strong>on</strong> the Rvs of<br />
bent<strong>on</strong>ite (Kunigel-V1) reported so far were analyzed. C<strong>on</strong>sequently, it was found that dry density of the bent<strong>on</strong>ite when<br />
the free swelling reached equilibrium state was approximately in the range of 0.204-0.241 kg/dm3 for distilled water<br />
c<strong>on</strong>diti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g>se dry densities are equivalent to the range of 0.106-0.126 kg/dm3 in m<strong>on</strong>tmorill<strong>on</strong>ite partial density. On<br />
the other hand, the Rvs of bent<strong>on</strong>ite decreased for saline water c<strong>on</strong>diti<strong>on</strong>. Based <strong>on</strong> these experimental data for Rvs, the<br />
author derived an analytical expressi<strong>on</strong> to be able to calculate Rvs values against various dry densities and bent<strong>on</strong>ites<br />
(different m<strong>on</strong>tmorill<strong>on</strong>ite and silica sand c<strong>on</strong>tents), and showed the manner for judging whether clearance is sealed for<br />
an arbitrary clearance ratio. In the paper, the author shows the calculated results of Rvs versus dry density under various<br />
c<strong>on</strong>diti<strong>on</strong>s.<br />
13) 40069 – Current Status of Hor<strong>on</strong>obe URL Project in C<strong>on</strong>structi<strong>on</strong> Phase<br />
Hir<strong>on</strong>obu Abe, Koichiro Hatanaka, JAEA (Japan)<br />
Hor<strong>on</strong>obe URL project has been pursued by JAEA (Japan Atomic Energy Agency) to establish and dem<strong>on</strong>strate site<br />
characterizati<strong>on</strong> methodologies, engineering technologies, and safety assessment methodologies for HLW geological<br />
disposal in relevant geological envir<strong>on</strong>ment with sedimentary rock and saline groundwater distributing in Hor<strong>on</strong>obe area,<br />
Hokkaido, Japan. In the Hor<strong>on</strong>obe URL project, surface-based investigati<strong>on</strong> phase (Phase I) has already completed in the<br />
year 2005, and then c<strong>on</strong>structi<strong>on</strong> phase (Phase II) has initiated in the same year. Currently, c<strong>on</strong>structi<strong>on</strong> of the<br />
underground facilities such as shafts/drifts which were designed in Phase I, investigati<strong>on</strong>s of the geological envir<strong>on</strong>ment<br />
in the excavated shafts/drifts and c<strong>on</strong>firmati<strong>on</strong> of applicability of engineering technologies has been alternately carried<br />
out as Phase II activities of the project. At the end of January, 2010, ventilati<strong>on</strong> shaft has reached at the depth of<br />
GL-250m and east access shaft has reached at the depth of GL210m. C<strong>on</strong>cerning horiz<strong>on</strong>tal drifts, c<strong>on</strong>structi<strong>on</strong> of<br />
GL-140m gallery with total length of 184m has completed and GL-250m gallery has partially c<strong>on</strong>structed with the length<br />
of 42m. During the c<strong>on</strong>structi<strong>on</strong> so far, m<strong>on</strong>itoring for the c<strong>on</strong>structi<strong>on</strong> safety such as c<strong>on</strong>vergence measurements, tunnel<br />
wall observati<strong>on</strong>, sampling of groundwater and rock, investigati<strong>on</strong>s for evaluating excavati<strong>on</strong> damaged z<strong>on</strong>e al<strong>on</strong>g<br />
shaft/drift were carried out. In additi<strong>on</strong>, shotcrete c<strong>on</strong>structi<strong>on</strong> test and grout injecti<strong>on</strong> test by using low alkaline cement<br />
material were carried in the horiz<strong>on</strong>tal drifts. In this paper, status of the URL c<strong>on</strong>structi<strong>on</strong> and research activities<br />
menti<strong>on</strong>ed above are outlined as the current achievement of the Hor<strong>on</strong>obe URL project.<br />
14) 40074 – Development of New Ultrafiltrati<strong>on</strong> Techniques Maintaining In-Situ Hydrochemical C<strong>on</strong>diti<strong>on</strong>s for<br />
Colloidal Study<br />
Daisuke Aosai, Yuhei Yamamoto, Takashi Mizuno, JAEA (Japan)<br />
Chemical state of elements in groundwater is <strong>on</strong>e of the most important informati<strong>on</strong> for understanding behavior of<br />
elements in underground envir<strong>on</strong>ment. Chemical state of elements c<strong>on</strong>trolled mainly by groundwater physico-chemical<br />
parameters. Because the change of physico-chemical parameters of groundwater, due to pressure release and oxidati<strong>on</strong><br />
during sampling, causes changes in chemical state of elements, systematic methodologies for understanding in situ<br />
chemical state is required. In this study, in order to understand chemical state of elements in groundwater, an<br />
ultrafiltrati<strong>on</strong> instrument for maintaining in-situ pressure and anaerobic c<strong>on</strong>diti<strong>on</strong>s was developed. <str<strong>on</strong>g>The</str<strong>on</strong>g> instrument<br />
developed in this study for ultrafiltrati<strong>on</strong> made of passivated Stainless Used Steel (SUS) materials, was designed to keep<br />
groundwater samples maintaining in-situ pressure/anaerobic c<strong>on</strong>diti<strong>on</strong>s. Ultrafiltrati<strong>on</strong> of groundwater was c<strong>on</strong>ducted at<br />
a borehole drilled from the 200 mbGL (meters below ground level) Sub-stage at a depth of 200 m at the Mizunami<br />
Underground Research Laboratory. Chemical analyses of groundwater were also c<strong>on</strong>ducted using samples filtered under<br />
both pressurized/anaerobic and atmospheric c<strong>on</strong>diti<strong>on</strong>s and passivated SUS materials with different elapsed times after<br />
passivati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> results indicate that our ultrafiltrati<strong>on</strong> method is suitable for collecti<strong>on</strong> of filtered groundwater and<br />
passivati<strong>on</strong> is an essential treatment before ultrafiltrati<strong>on</strong>. Keywords: groundwater, ultrafiltrati<strong>on</strong>.<br />
106
Abstracts<br />
15) 40089 – Sorpti<strong>on</strong> Behavior of Iodine <strong>on</strong> Calcium Silicate Hydrates Formed as a Sec<strong>on</strong>dary Mineral<br />
Keisuke Shirai, Yuichi Niibori, Akira Kirishima, Hitoshi Mimura, Tohoku Univ. (Japan)<br />
This study examined the sorpti<strong>on</strong> behaviors of iodine into CSH gel without dried processes, c<strong>on</strong>sidering the<br />
repository system saturated with groundwater after the backfilling. In glove box saturated with N2 gas, each sample of<br />
CSH gel was synthesized with CaO, SiO2, and distilled water with liquid/solid ratio 20. <str<strong>on</strong>g>The</str<strong>on</strong>g>n, 1 mM iodine soluti<strong>on</strong> is<br />
added into the aqueous soluti<strong>on</strong> including the CSH gel with various Ca/Si molar ratios under the isothermal c<strong>on</strong>diti<strong>on</strong><br />
(298 K).<br />
In the results, even if the Ca/Si ratio is relatively small (
Abstracts<br />
determined c<strong>on</strong>centrati<strong>on</strong> of Sn-126 was equivalent to 60% of that obtained by ORIGEN2 calculati<strong>on</strong>, which suggests<br />
that a part of Sn initially existed in the sample UO2 pellet precipitated as insoluble residue during the dissoluti<strong>on</strong> process.<br />
18) 40103 – Selective Uptake of Palladium from High-Level Liquid Wastes by Hybrid Microcapsules<br />
Hitoshi Mimura, Takashi Sakakibara, Yan Wu, Yuichi Niibori, Tohoku Univ. (Japan);<br />
Shin-ichi Koyama, Takashi Ohnishi, JAEA (Japan)<br />
Fine crystalline powders of KCuFC were immobilized with alginate gel polymers by sol-gel methods. <str<strong>on</strong>g>The</str<strong>on</strong>g> uptake<br />
properties of KCuFC-microcapsules (KCuFC-MC) were examined by batch and column methods. <str<strong>on</strong>g>The</str<strong>on</strong>g> size of<br />
KCuFC-MC particle was estimated to be about 1 mm in diameter, and KCuFC powders were uniformly dispersed in<br />
KCuFC-MC particles. <str<strong>on</strong>g>The</str<strong>on</strong>g> uptake rate of Pd2+ for KCuFC-MC was attained within 3 d, and the uptake of Pd2+ was<br />
found to be independent of the temperature and coexisting HNO3 c<strong>on</strong>centrati<strong>on</strong>. As for the breakthrough properties of<br />
Pd2+ through a column packed with KCuFC-MC, a breakpoint of 5% breakthrough was enhanced with lowering of flow<br />
rate and independent of coexisting HNO3 c<strong>on</strong>centrati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> Pd2+ i<strong>on</strong>s were selectively adsorbed in the KCuFC crystal<br />
phase, while other metal i<strong>on</strong>s such as Ru(NO)3+ and ZrO2+ were absorbed in the alginate phase. High uptake percentage<br />
of 98.6% was obtained by using the dissolved soluti<strong>on</strong>s of spent fuel from FBR-JOYO (119 GWd/t, JAEA). <str<strong>on</strong>g>The</str<strong>on</strong>g> alginate<br />
film enclosing KZnFC was further prepared by using the support of cellulose filter paper, where the Pd2+ i<strong>on</strong>s were<br />
selectively adsorbed <strong>on</strong> the KZnFC-MC film. <str<strong>on</strong>g>The</str<strong>on</strong>g> alginate film enclosing insoluble ferrocyanides are predicted for the<br />
selective separati<strong>on</strong> of Pd2+ as an i<strong>on</strong>-exchange filter. Thus, the microcapsules enclosing insoluble ferrocyanides are<br />
effective for the selective separati<strong>on</strong> of Pd2+ from high-level liquid waste (HLLW).<br />
19) 40113 – An Empirical Model To Determine <str<strong>on</strong>g>The</str<strong>on</strong>g> Modes Of Corrosi<strong>on</strong> Of Carb<strong>on</strong> Steel<br />
Toshikatsu Maeda, Masatoshi Watanabe, Seiji Takeda, Shinichi Nakayama, JAEA (Japan)<br />
Carb<strong>on</strong> steel is a candidate material for overpack of high-level radioactive waste disposal in Japan. One of its<br />
expected functi<strong>on</strong>s is to avoid groundwater from c<strong>on</strong>tacting with vitrified waste form. <str<strong>on</strong>g>The</str<strong>on</strong>g> corrosi<strong>on</strong> rate is a determining<br />
factor for the overpack lifetime, and it is highly dependent <strong>on</strong> the mode of corrosi<strong>on</strong>. Carb<strong>on</strong> steel is an alloy that could<br />
be attacked by localized corrosi<strong>on</strong> in the form of pitting corrosi<strong>on</strong> or crevice corrosi<strong>on</strong> under certain water chemistries.<br />
For example, it is known that carb<strong>on</strong> steel is passivated in soluti<strong>on</strong>s above a limiting pH; pH that is referred to as the<br />
general corrosi<strong>on</strong>/passivati<strong>on</strong> transiti<strong>on</strong> pH and is denoted as pHd. Carb<strong>on</strong> steel corrosi<strong>on</strong> rates depend <strong>on</strong> the mode of<br />
corrosi<strong>on</strong> (general or local corrosi<strong>on</strong>), which is determined by the pHd value. Predicting the pHd for carb<strong>on</strong> steel in near<br />
field envir<strong>on</strong>ments is essential to evaluate the expected lifetime of overpacks, especially c<strong>on</strong>sidering the possibility of<br />
highly alkaline envir<strong>on</strong>ments induced by cementitious materials in the disposal facility. In this study, an empirical model<br />
was developed to determine whether near field envir<strong>on</strong>ments fall in the passivati<strong>on</strong> or n<strong>on</strong>-passivati<strong>on</strong> domain for carb<strong>on</strong><br />
steel. Using the experimental data obtained by previous studies, the pHd was defined as a functi<strong>on</strong> of four factors shown<br />
in equati<strong>on</strong> (1), where the activity of prot<strong>on</strong> i<strong>on</strong> ([H+]) for pHd is assumed to be a linear combinati<strong>on</strong> of the logarithms of<br />
the total carb<strong>on</strong>ate c<strong>on</strong>centrati<strong>on</strong> (C total), the chloride i<strong>on</strong> c<strong>on</strong>centrati<strong>on</strong> (Cl-), and the limiting current density of<br />
dissolved oxygen diffusi<strong>on</strong> (iO2), and the inverse of absolute temperature of c<strong>on</strong>tacting soluti<strong>on</strong> (T). <str<strong>on</strong>g>The</str<strong>on</strong>g> derived<br />
equati<strong>on</strong> fitted well experimental data from previous studies.<br />
20) 40124 – Trends in Scenario Development Methodologies and Integrati<strong>on</strong> in NUMO's Approach<br />
Takeshi Ebashi, Katsuhiko Ishiguro,NUMO (Japan); Keiichiro Wakasugi, JAEA (Japan);<br />
Hideki Kawamura, Obayashi Corporati<strong>on</strong> (Japan);<br />
Irina Gaus, Stratis Vomvoris, Andrew Martin, Nagra (Switzerland);<br />
Paul Smith, Safety Assessment Management (UK)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> development of scenarios for quantitative or qualitative analysis is a key element of the assessment of the safety<br />
of geological disposal systems. As an outcome of an internati<strong>on</strong>al workshop attended by European and the Japanese<br />
implementers, a number of features comm<strong>on</strong> to current methodologies could be identified, as well as trends in their<br />
evoluti<strong>on</strong> over time. In the late nineties, scenario development was often described as a bottom-up process, whereby<br />
scenarios were said to be developed in essence from FEP databases. Nowadays, it is recognised that, in practice, the<br />
approaches actually adopted are better described as top-down or "hybrid", taking as their starting point an integrated<br />
(top-down) understanding of the system under c<strong>on</strong>siderati<strong>on</strong> including uncertainties in initial state, sometimes assisted by<br />
the development of "storyboards". A bottom-up element remains (hence the term "hybrid") to the extent that FEP<br />
databases or FEP catalogues (including interacti<strong>on</strong>s) are still used, but the focus is generally <strong>on</strong> completeness checking,<br />
which occurs parallel to the main assessment process. Recent advances focus <strong>on</strong> the c<strong>on</strong>sistent treatment of uncertainties<br />
throughout the safety assessment and <strong>on</strong> the integrati<strong>on</strong> of operati<strong>on</strong>al safety and l<strong>on</strong>g term safety.<br />
108
Abstracts<br />
21) 40137 – Development of Methodology to C<strong>on</strong>struct a Generic C<strong>on</strong>ceptual Model of River-valley Evoluti<strong>on</strong><br />
for Performance Assessment of HLW Geological Disposal<br />
Makoto Kawamura, Kenichi Yasue, Tadafumi Niizato, Shin-ichi Tanikawa, JAEA (Japan)<br />
In order to assess the l<strong>on</strong>g-term safety of a geological disposal system for high-level radioactive waste (HLW), it is<br />
important to c<strong>on</strong>sider the impact of uplift and erosi<strong>on</strong>, which cannot be precluded <strong>on</strong> a timescale in the order of several<br />
hundred thousand years for many locati<strong>on</strong>s in Japan. Geomorphic evoluti<strong>on</strong>, caused by uplift and erosi<strong>on</strong> and coupled to<br />
climatic and sea-level changes, will impact the geological disposal system due to resulting spatial and temporal changes<br />
in the disposal envir<strong>on</strong>ment. Degradati<strong>on</strong> of HLW barrier performance will be particularly significant when the remnant<br />
repository structures near, and are eventually exposed at, the ground surface. In previous studies, river erosi<strong>on</strong> was<br />
identified as the key c<strong>on</strong>cern in most settings in Japan. Here, therefore, we present a methodology for development of a<br />
generic c<strong>on</strong>ceptual model for performance assessment based <strong>on</strong> best current understanding of river erosi<strong>on</strong> in Japan.<br />
Critical c<strong>on</strong>siderati<strong>on</strong>s that have to be taken into account when interpreting the geological record of past river-valley<br />
evoluti<strong>on</strong>s, as preserved in ancient fluvial deposits, include: 1) the spatial variati<strong>on</strong> in the relative significance of erosi<strong>on</strong><br />
and sedimentati<strong>on</strong> at any time between upper- and lower-reaches of rivers originating in mountainous terrain 2) the<br />
temporal variati<strong>on</strong> in the extent of erosi<strong>on</strong> / sedimentati<strong>on</strong> at any specific locati<strong>on</strong> during glacial / interglacial cycles 3)<br />
the balance between uplift and vertical erosi<strong>on</strong> as a result of the hardness of the riverbed rock 4) the balance between<br />
vertical and lateral erosi<strong>on</strong> – ranging from formati<strong>on</strong> of narrow gorges to wide meandering flood plains 5) the varying<br />
durati<strong>on</strong> and intensity (as assessed by sea level change) of past glacial / interglacial cycles.<br />
Interpretati<strong>on</strong> of the impact of such phenomena at relevant locati<strong>on</strong>s in Japan has led to development of a generic<br />
c<strong>on</strong>ceptual model which c<strong>on</strong>tains the features typical of mid-reach rivers. This paper presents the methodology to<br />
develop the c<strong>on</strong>ceptual model, identifies the simplificati<strong>on</strong>s and uncertainties involved and assesses their c<strong>on</strong>sequences in<br />
the c<strong>on</strong>text of repository performance. Details of resultant analyses using this c<strong>on</strong>ceptual model will be discussed in<br />
another paper presented in ICEM’10 by Miyahara et al.<br />
22) 40162 – L<strong>on</strong>g-term Stability of Bent<strong>on</strong>ite Material Used as Engineered Barrier for Radioactive Waste<br />
Disposal<br />
Vera Jedinakova-Krizova, Katerina Videnska, Institute of Chemical Chechnology Prague (Czech Republic);<br />
Eduard Hanslik, T.G.M. Water Research Institute (Czech Republic)<br />
Geological c<strong>on</strong>cepts for the storage of radioactive waste are based <strong>on</strong> „multi-barrier“ systems, which are composed<br />
of several elements: the waste packaging, an engineered barrier incorporating bent<strong>on</strong>ite material and a geological barrier.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> stability of engineered barriers can be affected by l<strong>on</strong>g-term pressure and temperature gradients. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>tributi<strong>on</strong> is<br />
focused <strong>on</strong> geotechnical, chemical, geochemical and mineralogical research of bent<strong>on</strong>ite stability with the aim to<br />
determine the effect of saturati<strong>on</strong> medium compositi<strong>on</strong> and loading by heat <strong>on</strong> bent<strong>on</strong>ite stability. <str<strong>on</strong>g>The</str<strong>on</strong>g> main part the<br />
research is directed to the experimental results of bent<strong>on</strong>ite and bent<strong>on</strong>ite leachate samples obtained for the bent<strong>on</strong>ite<br />
interacti<strong>on</strong> under laboratory or in situ experiments. <str<strong>on</strong>g>The</str<strong>on</strong>g> tested bent<strong>on</strong>ite materials represent a series of compact loaded<br />
bent<strong>on</strong>ite samples taken from the dismantling process of the Mock-Up-Cz experiment, which c<strong>on</strong>stitute first vertical<br />
model of a bench-scale buffer mass test of Czech smectitic clay in the Europe. Mineralogical compositi<strong>on</strong>, chemical and<br />
physicochemical properties including uptake of l<strong>on</strong>g-term lived fissi<strong>on</strong> products in the form of 99TcO4- and 134Cs+<br />
were utilised for the evaluati<strong>on</strong> of the changes caused with the loading of this material. This work aims to characterise the<br />
basic parameters (i<strong>on</strong> exchange capacity, mineralogical and chemical compositi<strong>on</strong>, specific surface area) of bent<strong>on</strong>ite<br />
materials, which are important for the retenti<strong>on</strong> of the ani<strong>on</strong>ic forms of redox-sensitive radi<strong>on</strong>uclides (99Tc, 125I). In<br />
particular, i<strong>on</strong> exchange capacity characterises bent<strong>on</strong>ite’s ability to adsorb i<strong>on</strong>s from an aqueous envir<strong>on</strong>ment.<br />
Geological c<strong>on</strong>cepts for the storage of radioactive waste are based <strong>on</strong> „multi-barrier“ systems: the waste packaging, an<br />
engineered barrier incorporating bent<strong>on</strong>ite material and a geological barrier. <str<strong>on</strong>g>The</str<strong>on</strong>g> stability of engineered barriers can be<br />
affected by l<strong>on</strong>g-term pressure and temperature gradients. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>tributi<strong>on</strong> is focused <strong>on</strong> geotechnical, chemical,<br />
geochemical and mineralogical research of bent<strong>on</strong>ite stability with the aim to determine the effect of saturati<strong>on</strong> medium<br />
compositi<strong>on</strong> and loading by heat <strong>on</strong> bent<strong>on</strong>ite stability. <str<strong>on</strong>g>The</str<strong>on</strong>g> main part the research is directed to the experimental results<br />
of bent<strong>on</strong>ite and bent<strong>on</strong>ite leachate samples obtained for the bent<strong>on</strong>ite interacti<strong>on</strong> under laboratory or in situ experiments.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> tested bent<strong>on</strong>ite materials represent a series of compact loaded bent<strong>on</strong>ite samples taken from the dismantling process<br />
of the Mock-Up-Cz experiment, which c<strong>on</strong>stitute first vertical model of a bench-scale buffer mass test of Czech smectitic<br />
clay in the Europe. Mineralogical compositi<strong>on</strong>, chemical and physicochemical properties including uptake of l<strong>on</strong>g-term<br />
lived fissi<strong>on</strong> products in the form of 99TcO4- and 134Cs+ were utilised for the evaluati<strong>on</strong> of the changes caused with the<br />
loading of this material. It was found that bent<strong>on</strong>ite material was stable from the point of the l<strong>on</strong>g term loading under the<br />
model c<strong>on</strong>diti<strong>on</strong>s applied in the Mock-Up-Cz experiment and <strong>on</strong>ly small part of original bent<strong>on</strong>ite material was<br />
transformed under the occurrence of the newly formed mineral domains (about few weight percent) as result of the l<strong>on</strong>g<br />
term loading bent<strong>on</strong>ite material by pressure and temperature gradients. It can be c<strong>on</strong>cluded that listed above newly<br />
formed mineral phases originated by transformati<strong>on</strong> of bent<strong>on</strong>ite material have no significant influence <strong>on</strong> the i<strong>on</strong><br />
exchange properties. Migrati<strong>on</strong> studies of 99TcO4-and 134Cs+ simultaneously c<strong>on</strong>firmed these results, as well. Similar<br />
behaviour of bent<strong>on</strong>ite clay barrier can be expected in the l<strong>on</strong>g time therefore this material is suitable for the applicati<strong>on</strong>s<br />
as engineered barrier in the deep repository of the high level radioactive waste and spent fuel.<br />
Acknowledgement: This research was supported by the Ministry of Educati<strong>on</strong>, Youth and Sports of Czech Republic<br />
under the project MSM 60461373007 and by Ministry of Industry and Trade under the project FR-TI1/362.<br />
109
Abstracts<br />
23) 40173 – Development of a methodology for evaluating the performance of host rock for geological disposal<br />
based <strong>on</strong> surface-based investigati<strong>on</strong>s<br />
Manabu Inagaki, Keisuke Maekawa, JAEA (Japan);<br />
Tatsuya Tanaka, Shuji Hashimoto, Obayashi Corporati<strong>on</strong> (Japan)<br />
In most countries, a step-wise site investigati<strong>on</strong> strategy is applied (or planned) in the site selecti<strong>on</strong> process for<br />
geological disposal of HLW. In Japan, preliminary surface-based investigati<strong>on</strong>s such as boreholes and geophysical<br />
surveys will be followed by detailed investigati<strong>on</strong>s, including c<strong>on</strong>structi<strong>on</strong> of, and testing in, an underground<br />
characterizati<strong>on</strong> facility. Such investigati<strong>on</strong>s assess compliance with legal requirements and provide the understanding of<br />
geological c<strong>on</strong>diti<strong>on</strong>s needed for the development of a repository c<strong>on</strong>cept. <str<strong>on</strong>g>The</str<strong>on</strong>g> repository c<strong>on</strong>cept, including<br />
underground design and layout, will depend <strong>on</strong> the spatial extent of the candidate rock formati<strong>on</strong>(s) and their barrier<br />
performance under site-specific c<strong>on</strong>diti<strong>on</strong>s found deep underground. However, informati<strong>on</strong> obtained from initial<br />
surface-based investigati<strong>on</strong>s is inherently limited and includes uncertainties, particularly with regard to the heterogeneity<br />
of geological characteristics. It is thus important to assess host rock performance in a manner that explicitly c<strong>on</strong>siders<br />
uncertainties in the site characterizati<strong>on</strong>.<br />
In this study, methodology for evaluati<strong>on</strong> of geological c<strong>on</strong>diti<strong>on</strong>s has been developed that focuses <strong>on</strong> determining<br />
the usable volume of host rock with specific performance characteristics. A test case utilizes the dataset obtained from<br />
the Hor<strong>on</strong>obe Underground Research Laboratory Project, which is selectively used by taking into c<strong>on</strong>siderati<strong>on</strong> step-wise<br />
data producti<strong>on</strong> of a type that would result from preliminary surface-based investigati<strong>on</strong>s. Initially, multiple performance<br />
indices - such as groundwater velocity and solute transport distance -have been defined as key characteristics of the<br />
geological envir<strong>on</strong>ment from the viewpoint of barrier performance. Based <strong>on</strong> the interpretati<strong>on</strong> of the dataset, alternative<br />
hydrogeological c<strong>on</strong>ceptualizati<strong>on</strong>s are developed, resulting in several different hydrogeological models. <str<strong>on</strong>g>The</str<strong>on</strong>g> critical<br />
issue of understanding the impact of uncertainty described in hydrogeological model is addressed by assessment using a<br />
particle tracking method, which allows quantificati<strong>on</strong> of the sensitivity of the performance indices to these uncertainties.<br />
Finally, a radi<strong>on</strong>uclide migrati<strong>on</strong> model was included to further assess the significance of the performance indicators in<br />
characterizing the impact of hydrogeological uncertainties <strong>on</strong> the safety of a repository.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> performance indices proposed in this study are seen to be useful to identify requirements and focus<br />
investigati<strong>on</strong> for the selecti<strong>on</strong> of host rocks. Assessing the impact of uncertainties of c<strong>on</strong>ceptualizati<strong>on</strong> of the<br />
hydrogeology <strong>on</strong> the performance indices and nuclide migrati<strong>on</strong> then leads to a better understanding of critical issues in<br />
determining the usable volume of potential host rocks.<br />
24) 40176 – Structural Integrity Evaluati<strong>on</strong> Approach for PWR Spent Nuclear Fuel<br />
Yun Seog Nam, Se<strong>on</strong>g Ki Lee, Y<strong>on</strong>g Hwan Kim, Je<strong>on</strong> Kye<strong>on</strong>g Lak,<br />
Choi Ki Sung, Chang Sok Cho, KNF (Korea Rep.)<br />
PWR fuel assembly experiences many changes from the time it is manufactured, loaded in the reactor and<br />
repositi<strong>on</strong>ed in the core several times until finally removed from the reactor for the interim storage, reprocessing or final<br />
disposal etc. Under a severe radiati<strong>on</strong> and a thermo-mechanical c<strong>on</strong>diti<strong>on</strong>, this mechanism can alter fuel assembly<br />
characteristics such as its mechanical properties, geometrical shape, material characteristics etc. Any of these alterati<strong>on</strong>s<br />
which impact spent nuclear fuel (SNF) integrity should be c<strong>on</strong>sidered to design a cask/canister for its transportati<strong>on</strong> or<br />
intermediate dry storage. Regarding the cask/canister design, there could be a freedom to design a system that mitigates<br />
the forces transmitted to SNF and fuel rods. If the storage cask/canister or transport package design prevents or mitigates<br />
forces transmitted to its c<strong>on</strong>tents such that structural integrity is not significantly compromised, the detailed SNF<br />
properties are necessary to make a decisi<strong>on</strong> of the elaborated design parameters, assuming other factors (temperature,<br />
inert atmosphere, etc.) have been adequately addressed. An approach to those work formati<strong>on</strong>s is to analyze mechanical<br />
characteristics of structural comp<strong>on</strong>ents which are the mechanical properties of grid spring reflecting its irradiati<strong>on</strong> effect,<br />
SNF strength and SNF structural deformati<strong>on</strong> such as its bow, twist etc. Those informati<strong>on</strong>s are also used to evaluate<br />
hypothetical accident like a drop accident of SNF cask/canister, to select limiting fuel assembly for cask/canister to<br />
accommodate various kinds of SNFs and to design transportati<strong>on</strong> or storage system for SNFs. Especially, the fuel<br />
assembly structural properties are a sort of essential data. Thus, in this paper, some approaches to evaluate SNF<br />
mechanical characteristics are suggested through the existing technical informati<strong>on</strong> review, some test data and the<br />
analysis methodology, and also closely study the mechanical characteristics of a representative SNF for its general<br />
comprehensi<strong>on</strong>.<br />
25) 40200 – Development of Program Categories to Assess the Radiological Dosage during Spent Fuel<br />
Transportati<strong>on</strong><br />
Suh<strong>on</strong>g Lee , Sangw<strong>on</strong> Shin, Enesys, Jaemin Lee, Enesys.Co.,Ltd. (Korea Rep.);<br />
Kiyroul Se<strong>on</strong>g, Je<strong>on</strong>ghyoun Yo<strong>on</strong>, KRMC (Korea Rep.)<br />
Korea is seeking the plan to put spent fuels in interim storage facility as disposal business of low and<br />
intermediate-Level radioactive waste started. First, <str<strong>on</strong>g>The</str<strong>on</strong>g>re is a str<strong>on</strong>g probability that transport of the spent fuels will be<br />
arranged in marine transportati<strong>on</strong>. Accordingly, building of transportati<strong>on</strong> risk assessment system in the marine<br />
transportati<strong>on</strong> comes to the force as a real problem. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, in this study, I organized the basic categories of program<br />
110
Abstracts<br />
to develop transportati<strong>on</strong> risk assessment program about specialized transport in marine transportati<strong>on</strong> of spent fuels. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
possibility of radiati<strong>on</strong> exposure in marine transportati<strong>on</strong> c<strong>on</strong>sists of the normal c<strong>on</strong>diti<strong>on</strong> and the accident c<strong>on</strong>diti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
direct radiati<strong>on</strong> exposure that the workers in loading and crews of the vessels will receive is c<strong>on</strong>sidered in the normal<br />
c<strong>on</strong>diti<strong>on</strong>. I decide the leakage rate dividing the accident c<strong>on</strong>diti<strong>on</strong> that the radioactive materials are spilled into air and<br />
marine and doing the effect by emissi<strong>on</strong> by fire and physical damage. Also, as for the radioactive materials floated in the<br />
air, calculated applying the atmospheric dispersi<strong>on</strong> factors to them and evaluate the direct radiati<strong>on</strong> exposure and internal<br />
radiati<strong>on</strong> exposure. As for marine c<strong>on</strong>taminati<strong>on</strong>, the radioactive materials move al<strong>on</strong>g ocean currents. Generally, there<br />
can be the direct radiati<strong>on</strong> exposure of ocean activists due to the moving radioactive materials according to the flow of<br />
the ocean currents in c<strong>on</strong>taminated marine and the direct radiati<strong>on</strong> exposure and the indirect radiati<strong>on</strong> exposure by<br />
breathing of the subjects near the shores due to the smoke and fog form that occurs by seawater. Also the internal<br />
radiati<strong>on</strong> exposure by intake c<strong>on</strong>tains <strong>on</strong>e of marine life. I set the categories to build the overall programs to build this<br />
with the comprehensive program that have effects <strong>on</strong> radiati<strong>on</strong> while the spent fuels are transported combining it with the<br />
transport c<strong>on</strong>diti<strong>on</strong>s or the characteristics of the subjects of radiati<strong>on</strong> exposure and the envir<strong>on</strong>mental factors. And<br />
building of the program will be completed through it. <str<strong>on</strong>g>The</str<strong>on</strong>g> completed program can evaluate various c<strong>on</strong>diti<strong>on</strong>s of marine<br />
transportati<strong>on</strong> after it will be specialized in marine transportati<strong>on</strong>.<br />
26) 40225 – Exploiting synergies between the UK & Japanese geological disposal programmes<br />
Ellie Scourse, Atkins (UK); Hideki Kawamura, Obayashi Corporati<strong>on</strong> (Japan);<br />
Ian G. McKinley, McKinley C<strong>on</strong>sulting (Switzerland)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> early ‘80s UK programme for deep geological disposal of high-level radioactive waste was advanced and at the<br />
stage of characterising potential sites. When this project was put <strong>on</strong> hold in the mid ‘80s, much expertise in this field was<br />
lost.<br />
In Japan R&D in the ‘80s resulted in major generic safety assessments to dem<strong>on</strong>strate feasibility in the ‘90s. This<br />
led to the establishment of NUMO (Nuclear Waste Management Organizati<strong>on</strong> of Japan) and the initiati<strong>on</strong> of siting based<br />
<strong>on</strong> volunteerism. This novel approach required more flexible methodology and tools for site characterisati<strong>on</strong>, repository<br />
design and safety assessment. NUMO and supporting R&D organisati<strong>on</strong>s in Japan have invested much time and effort<br />
preparing for volunteers but, unfortunately, no discussi<strong>on</strong>s with potential host communities have yet developed to the<br />
point where technical work is initiated.<br />
Presently, the UK is moving forward; with the NDA RWMD (Nuclear Decommissi<strong>on</strong>ing Agency Radioactive<br />
Waste Management Directorate) adopting a NUMO-style volunteering approach and a flexible design catalogue.<br />
Communities have already shown interest in volunteering. <str<strong>on</strong>g>The</str<strong>on</strong>g> situati<strong>on</strong> is thus ideal for collaborati<strong>on</strong>.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> paper will expand <strong>on</strong> the opportunities for the UK and Japan to benefit from an active collaborati<strong>on</strong> and discuss<br />
how this can be most efficiently implemented.<br />
Key Words: UK, Japan, collaborati<strong>on</strong><br />
27) 40239 – Realistic C<strong>on</strong>sequence Analysis of River Erosi<strong>on</strong> Scenarios for a HLW epository<br />
Kaname Miyahara , Makoto Kawamura, Manabu Inagaki, JAEA (Japan);<br />
Ian G. McKinley, McKinley C<strong>on</strong>sulting (Switzerland);<br />
Michael J. Apted, M<strong>on</strong>itor Scientific LLC (USA)<br />
Uplift and erosi<strong>on</strong> cannot be precluded in most sites in Japan. As no assessment cut-off times have yet been defined,<br />
erosive radi<strong>on</strong>uclide release scenarios must be developed and analyzed, even if these occur far in the future. Obviously,<br />
uplift and erosi<strong>on</strong> will cause major disrupti<strong>on</strong> of the engineered and natural barriers when the repository nears, and is<br />
eventually exposed at, the ground surface. In a previous study, a simple linear uplift process was combined with a more<br />
detailed assessment of river erosi<strong>on</strong>, which was identified as the key erosi<strong>on</strong> process in Japan. This indicated the<br />
robustness of the reference HLW disposal system: the c<strong>on</strong>sequences of erosi<strong>on</strong> of the repository being small when<br />
compared to the yardstick provided by natural radi<strong>on</strong>uclide fluxes.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> original model was rather simple, but highlighted the importance of cyclic erosi<strong>on</strong> in resp<strong>on</strong>se to the changing<br />
envir<strong>on</strong>ment in glacial and inter-glacial periods. <str<strong>on</strong>g>The</str<strong>on</strong>g>refore, the geological record of such cycles preserved in Japan as<br />
river terraces has been studied further, with the aim of c<strong>on</strong>structing a more realistic river erosi<strong>on</strong> model. It is evident that,<br />
although riverbed deepening occurs during glacial cycles, significant sedimentati<strong>on</strong> also occurs and the timing of these<br />
phases during the cycle differs in the upper and lower reaches of rivers. Unfortunately the situati<strong>on</strong> is particularly<br />
complicated in mid-reach settings – and these may be most relevant for repositories that avoid mountain locati<strong>on</strong>s and<br />
cannot be established in the highly populated coastal plains. Here interpretati<strong>on</strong> of complex river terrace structures must<br />
take into account both variati<strong>on</strong>s in the length of past glacial/inter-glacial periods and in the resistance of different<br />
riverbeds to erosi<strong>on</strong>. Further, when the width of river channel is significantly less than that of the valley, meanders<br />
develop giving sequences of river terraces that are observed <strong>on</strong>ly <strong>on</strong> <strong>on</strong>e side (asymmetric) or <strong>on</strong> both sides (symmetric)<br />
of river. Unlike in the upper reaches, in such envir<strong>on</strong>ments it cannot be assumed that valley profiles are effectively<br />
c<strong>on</strong>stant in time and the gradual progress from eroding mountains towards formati<strong>on</strong> of a peneplain has to be c<strong>on</strong>sidered.<br />
This paper describes a c<strong>on</strong>ceptual model based <strong>on</strong> generalizati<strong>on</strong> of these observati<strong>on</strong>s and resultant c<strong>on</strong>sequence<br />
analyses, again using comparis<strong>on</strong>s with natural radi<strong>on</strong>uclide fluxes. Geological evidence supporting such erosi<strong>on</strong> models<br />
will be discussed in another paper presented in ICEM’10 by Kawamura et al.<br />
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28) 40272 – Removal of Fissi<strong>on</strong> Products in the Spent Electrolyte Using Ir<strong>on</strong> Phosphate Glass as a Sorbent<br />
Ippei Amamoto, Masami Nakada, Yoshihiro Okamoto, JAEA (Japan);<br />
Naoki Mitamura, Tatsuya Tsuzuki, Central Glass Co. Ltd. (Japan);<br />
Yasushi Takasaki, Atsushi Shibayama, Akita University (Japan);<br />
Tetsuji Yano, Tokyo Institute of Technology (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> [3LiCl(59.5mol%)-2KCl(40.5mol%)] eutectic medium used in the pyroreprocessing by the electrorefining method will be<br />
c<strong>on</strong>taminated by the accumulati<strong>on</strong> of various actinoid elements (An) and fissi<strong>on</strong> products (FP) due to prol<strong>on</strong>ged electrolytic operati<strong>on</strong>.<br />
Though the An can be removed at the pyroc<strong>on</strong>tactor step by extracti<strong>on</strong> using cadmium melt, the FP remain in the eutectic medium,<br />
which is regarded as a spent electrolyte at certain stage, can cause the rising of the melting point of the electrolytic bath and /or<br />
lowering the current efficiency. Some measures e.g., its replacement by a virgin medium, etc. should be taken to maintain its stable<br />
c<strong>on</strong>diti<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> c<strong>on</strong>stant replacement of the electrolyte, however, could lead to the generati<strong>on</strong> of enormous volume of high-level<br />
radioactive waste (HLW). In terms of envir<strong>on</strong>mental load reducti<strong>on</strong> and ec<strong>on</strong>omical improvement, it is desirable to have the spent<br />
electrolyte purified for recycling by removing its FP. Some technical developments <strong>on</strong> spent electrolyte treatments have been carried<br />
out in several countries. One of them is the zeolite sorpti<strong>on</strong> of FP following An removal which is being developed in the USA, Japan,<br />
etc.. Meanwhile, the c<strong>on</strong>taminants precipitati<strong>on</strong> methods by c<strong>on</strong>verting c<strong>on</strong>taminants to insoluble compounds are undertaken in Russia<br />
and a few other countries and are anticipated to reduce the total volume of HLW. In the case of the Russian process, its purpose is to<br />
remove c<strong>on</strong>taminants such as the minor actinoids (MA) and rare earth elements (REE) from the medium before its disposal. In our<br />
case, the main objective is to recycle the purified medium, delaying its disposal for as l<strong>on</strong>g as possible. It is with this objective in mind<br />
that this study was undertaken. We have introduced the simple filtrati<strong>on</strong> method to remove REE particles which were formed due to<br />
the c<strong>on</strong>versi<strong>on</strong> of REE chlorides to phosphates. Here, the ir<strong>on</strong> phosphate glass is used as a filtrati<strong>on</strong> medium for the removal of FP<br />
particles. However, some soluble FP such as compounds of alkali-metals, alkaline-earth metals, etc. still remain in the eutectic medium.<br />
This time around, <strong>on</strong> an experimental basis, the ir<strong>on</strong> phosphate glass has been used as a sorbent instead, to remove the soluble FP. We<br />
have obtained some positive results and have intenti<strong>on</strong> to incorporate it into the spent electrolyte recycle process as a part of the FP<br />
separati<strong>on</strong> and immobilizati<strong>on</strong> system.<br />
29) 40295 – Propagati<strong>on</strong> and Interacti<strong>on</strong>s of Acoustic Waves in a Waveguide Attached at the Surface of Rock<br />
Jin-Seop Kim, Kyung-Soo Lee, S. Kw<strong>on</strong>, KAERI (Korea Rep.); Gye-Chun Cho, KAIST (Korea Rep.)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> dynamic resp<strong>on</strong>se of a rock mass is inevitable in the systematic l<strong>on</strong>g-term m<strong>on</strong>itoring and management in the<br />
radioactive waste disposal repository. With this point of view, AE (acoustic emissi<strong>on</strong>) detecti<strong>on</strong> is c<strong>on</strong>sidered to be a<br />
promising technique for m<strong>on</strong>itoring the in-situ performance of near-field rock mass. In this study, propagati<strong>on</strong> and<br />
interacti<strong>on</strong>s of guided acoustic waves in a waveguide, which is required to in-situ applicati<strong>on</strong> of AE m<strong>on</strong>itoring system<br />
were investigated. <str<strong>on</strong>g>The</str<strong>on</strong>g> changes in acoustic wave amplitude, time delay, frequency variati<strong>on</strong>, and system transfer functi<strong>on</strong><br />
were measured between the waveguide and a rock sample. Subsequently the waveguide coupling c<strong>on</strong>diti<strong>on</strong>s filled with<br />
epoxy were compared with mechanical type of coupling for the validity of field applicati<strong>on</strong>. Three type of coupling<br />
methods were used to compare each other. One is a type of direct c<strong>on</strong>tact with granite specimen(Ch.2) which is same<br />
kind of rock mass with KURT(Korea Underground Research Tunnel) by using a vacuum grease as a reference data.<br />
Another is a waveguide-aided c<strong>on</strong>necti<strong>on</strong> method without any coupling fluid(Ch.1) and the other is a same type with<br />
Ch.1 except for the use of epoxy resin for a coupling fluid between the gap of a specimen and a waveguide. <str<strong>on</strong>g>The</str<strong>on</strong>g> time<br />
delay between CH.1 and CH.2 was 0.025 msec and in case of CH.3 and CH.2 0.012 msec. Energy decay ratio of first<br />
arrival signal for CH.1/CH.2 was 0.68 and 0.81 for CH.3/CH.2. Normalized amplitude attenuati<strong>on</strong> model with a distance<br />
was successfully obtained. <str<strong>on</strong>g>The</str<strong>on</strong>g> similarity of two signals were quantified using a mathematical tool called mean<br />
magnitude squared coherence(MSC). <str<strong>on</strong>g>The</str<strong>on</strong>g> mean MSC between CH.1-CH.6, CH.2-CH.6, and CH.3-CH.6 are 0.8727,<br />
0.9262 and 0.9040 respectively. <str<strong>on</strong>g>The</str<strong>on</strong>g> signal directly attached to the surface of a specimen presents the most similar<br />
pattern with the applied source signal. While the signals from the epoxy filled waveguide show closer relati<strong>on</strong>ship with<br />
the source than that without filling couplant. Additi<strong>on</strong>ally by using of system transfer functi<strong>on</strong>, the effect of waveguide is<br />
apparently shown at the frequency of 118 kHz. <str<strong>on</strong>g>The</str<strong>on</strong>g> results derived from this study can be valuable informati<strong>on</strong> for the<br />
quantitative analysis of signal processing in AE source localizati<strong>on</strong> and degree of crack damage in a radioactive waste<br />
repository.<br />
SESSION D7: D&D Poster<br />
1) 40009 – Decommissi<strong>on</strong>ing of the KRR-1 & 2 Research Reactors at KAERI; Summary <strong>on</strong> the Project<br />
Jin Ho Park, KAERI (Korea Rep.)<br />
At the Korea Atomic Energy Research Institute (KAERI), two research reactors (KRR-1 and KRR-2) have been<br />
decommissi<strong>on</strong>ed. <str<strong>on</strong>g>The</str<strong>on</strong>g> first research reactor in Korea, KRR-1, was a TRIGA MARK-II type (open pool and fixed core),<br />
112
Abstracts<br />
and its power was 100 kWt at its c<strong>on</strong>structi<strong>on</strong> and it was up-graded to 250 kWt by KAERI. <str<strong>on</strong>g>The</str<strong>on</strong>g> sec<strong>on</strong>d reactor, KRR-2,<br />
was a TRIGA MARK-III type with an open pool and a movable core and its power was 2 MWt. Its first criticality was<br />
reached in 1972 and it had been operated for 55,000 hours till the decisi<strong>on</strong> to shut it down in 1995. In 1996, it was<br />
c<strong>on</strong>cluded that KRR-1 and KRR-2 would be dismantled. A project was launched for the decommissi<strong>on</strong>ing of these<br />
reactors in January 1997 with the goal of a completi<strong>on</strong> by 2008. <str<strong>on</strong>g>The</str<strong>on</strong>g> total budget for the project is 20.0 milli<strong>on</strong> US<br />
dollars, including the cost for the waste disposal and for the development of the technologies. <str<strong>on</strong>g>The</str<strong>on</strong>g> work scopes during the<br />
reactor decommissi<strong>on</strong>ing project are the dismantling of all the facilities and the removal of all the radioactive materials<br />
from the reactor site. After c<strong>on</strong>firming the removal of the entire radioactivity by the MARSSIM c<strong>on</strong>cept, the site and<br />
buildings will be released for an unrestricted use after the approval of the regulatory body. This paper summarizes <strong>on</strong> the<br />
time tables, technologies, waste generati<strong>on</strong> and treatment, manpower c<strong>on</strong>sumpti<strong>on</strong>, cost and radiati<strong>on</strong> of work force and<br />
analyzes the performance <strong>on</strong> the base of the original plan.<br />
2) 40075 – Methods of Selected Input Calculati<strong>on</strong> Data Verificati<strong>on</strong> And <str<strong>on</strong>g>The</str<strong>on</strong>g>ir Influence On Decommissi<strong>on</strong>ing<br />
Cost In the OMEGA Code<br />
Frantisek Ondra. Vladimir Daniska, Ivan Rehak, Oto Schultz, DECONTA, a.s. (Slovakia);<br />
Vladimir Necas, Slovak University of Technology in Bratislava (Slovakia)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> aim of this c<strong>on</strong>tributi<strong>on</strong> is development of methodology for verificati<strong>on</strong> of selected input calculati<strong>on</strong> data<br />
(performance unit parameters, work group structure, and durati<strong>on</strong> of time-dependent activities) of the OMEGA Code in<br />
the individual PSL (Proposed Standardised List) structure parts. <str<strong>on</strong>g>The</str<strong>on</strong>g> OMEGA Code, developed by DECOM, a.s., is used<br />
for calculati<strong>on</strong> of nuclear power plant decommissi<strong>on</strong>ing parameters and decommissi<strong>on</strong>ing planning. <str<strong>on</strong>g>The</str<strong>on</strong>g> code represents<br />
a complex tool modelling a real flow of materials and radioactivity in the whole process of decommissi<strong>on</strong>ing, beginning<br />
from pre-dismantling dec<strong>on</strong>taminati<strong>on</strong> and terminating with either final disposal of radioactive waste or release of<br />
n<strong>on</strong>-c<strong>on</strong>taminated materials to the envir<strong>on</strong>ment. <str<strong>on</strong>g>The</str<strong>on</strong>g> analytical methodology for evaluati<strong>on</strong> of input data inaccuracy<br />
impacting <strong>on</strong> calculati<strong>on</strong> of cost and other output decommissi<strong>on</strong>ing parameters was developed. This methodology is<br />
based <strong>on</strong> applicati<strong>on</strong> of coefficients representing calculated cost relative change for c<strong>on</strong>tingency adjustment purpose. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
decommissi<strong>on</strong>ing process includes significant amount of various technical as well s administrative activities.<br />
Decommissi<strong>on</strong>ing parameters calculati<strong>on</strong> is performed by calculati<strong>on</strong> procedures modelling these decommissi<strong>on</strong>ing<br />
activities. <str<strong>on</strong>g>The</str<strong>on</strong>g> procedures use for calculati<strong>on</strong> a lot of input and unit data. Decommissi<strong>on</strong>ing calculati<strong>on</strong> parameters<br />
projects having been performed using the OMEGA Code showed the necessity of development of a new verificati<strong>on</strong><br />
module. This module is able to display selected input data used for calculati<strong>on</strong> for either specific inventory database item<br />
or specific decommissi<strong>on</strong>ing activity in the PSL structure. <str<strong>on</strong>g>The</str<strong>on</strong>g> new verificati<strong>on</strong> module allows compare selected input<br />
parameters to reference values including graphic display of differences. <str<strong>on</strong>g>The</str<strong>on</strong>g>re is also a possibility to perform<br />
recalculati<strong>on</strong> of the some decommissi<strong>on</strong>ing opti<strong>on</strong> using reference values of input data and c<strong>on</strong>sequently to compare<br />
calculated decommissi<strong>on</strong>ing data. <str<strong>on</strong>g>The</str<strong>on</strong>g>se data (e.g. exposure, labor, and cost) and their differences can be compared both<br />
in tables and graphs, for either specific inventory database item or specific PSL activity. <str<strong>on</strong>g>The</str<strong>on</strong>g> verificati<strong>on</strong> module within<br />
the OMEGA Code brings a new view <strong>on</strong> impact of selected input data change <strong>on</strong> calculated decommissi<strong>on</strong>ing data. It is<br />
auxiliary tool for c<strong>on</strong>tingency calculati<strong>on</strong> using analytical methods developed last year.<br />
3) 40078 – Experience of MR and RFT Reactors’ Decommissi<strong>on</strong>ing in RRC “Kurchatov Institute”<br />
Alexander V. Chesnokov,Victor Volkov, Sergey Semenov, Vitaly Pavlenko, Vyacheslav Kolyadin,<br />
D. Muzrukova, RRC "Kurchatov Institute" (Russia);Artur Arustamov, SUE SIA "Rad<strong>on</strong>" (Russia)<br />
Research channel-type nuclear reactor «MR» has been developed and commissi<strong>on</strong>ed in Russian Research Centre<br />
«Kurchatov Institute» in 1962-1963. "MR" reactor replaced the old <strong>on</strong>e -"RTF" type reactor. MR is <strong>on</strong>e of 12 units<br />
located in Kurchatov Institute. It started the operati<strong>on</strong> in 1963, and shut down in 1992. Reactor is located in the water<br />
pool <strong>on</strong> the 9 m depth. Nine loop units with different cooling medium are the experimental basis of MR. When MR has<br />
been shut down; the loop channels were disc<strong>on</strong>nected and placed into water pool. Nuclear fuel has been unloaded and<br />
moved to the dry repository. Decommissi<strong>on</strong>ing design has been developed by Russian Research Centre «Kurchatov<br />
institute» and JSC «Alliance-Gamma» in 2009 year. According to the decommissi<strong>on</strong>ing design the final state of reactor<br />
MR will come to: - Equipment and systems of reactor shall be dismantled completely; - Technological facilities of<br />
reactor and MR territory shall be dec<strong>on</strong>taminated and remediated according to the regulati<strong>on</strong>s. D&D design has been<br />
approved by Russian Authority in July 2009 year. In August 2009 the equipment supply and preliminary works have<br />
been started. Dismantling works are scheduled to start in 2011. Features of the reactor MR which have made an essential<br />
impact <strong>on</strong> the development of the project <strong>on</strong> decommissi<strong>on</strong>ing are shown. A status <strong>on</strong> decommissi<strong>on</strong>ing of reactors MR<br />
and RTF is resulted. <str<strong>on</strong>g>The</str<strong>on</strong>g> work performed <strong>on</strong> the reactor MR in preparati<strong>on</strong> for decommissi<strong>on</strong>ing, which include: removal<br />
of irradiated fuel from near reactor storage, disposal units of loop channels, acting above the water surface in a pool<br />
storage are described, identificati<strong>on</strong>, sorting and disposal of radioactive objects from gateway of the reactor is carried out.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> technologies for dismantling works were identified and the stages of work <strong>on</strong> the decommissi<strong>on</strong>ing of reactors MR<br />
and RTF is presented. <str<strong>on</strong>g>The</str<strong>on</strong>g> assessment of radiati<strong>on</strong> effects <strong>on</strong> the populati<strong>on</strong> and the envir<strong>on</strong>ment during the dismantling<br />
operati<strong>on</strong>s, which is determined by the amount of dismantling operati<strong>on</strong>s, the level of radioactive c<strong>on</strong>taminati<strong>on</strong> of the<br />
reactor structures and equipment, as well as the technologies used for their removal is completed. <str<strong>on</strong>g>The</str<strong>on</strong>g> results of the<br />
estimati<strong>on</strong> of radiati<strong>on</strong> effects <strong>on</strong> the populati<strong>on</strong> and the envir<strong>on</strong>ment during routine operati<strong>on</strong> to dismantle the<br />
equipment and in emergency situati<strong>on</strong>s are reduced.<br />
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Abstracts<br />
4) 40126 – Detailed Standardized Decommissi<strong>on</strong>ing Parameters Calculati<strong>on</strong> for Larger echnological Aggregates<br />
and Relevant Buildings in Nuclear Power Plants using the OMEGA Code<br />
Peter Bezak, Vladimir Daniska, DECONTA, a.s. (Slovakia); Ivan Rehak, DECOM, a.s. (Slovakia)<br />
Computer code OMEGA, developed by DECOM a.s., is used for evaluati<strong>on</strong> of nuclear facility decommissi<strong>on</strong>ing<br />
activities. <str<strong>on</strong>g>The</str<strong>on</strong>g> Code implements in full extent the standardised cost structure PSL. Decommissi<strong>on</strong>ing activities of nuclear<br />
facility are involved in compact calculati<strong>on</strong> structure. Calculati<strong>on</strong> models a real material and radioactivity flow and<br />
reflects a radioactivity decay during decommissi<strong>on</strong>ing process. Calculati<strong>on</strong> processes material items, which are linked to<br />
decommissi<strong>on</strong>ing procedures (dismantling, demoliti<strong>on</strong> and dec<strong>on</strong>taminati<strong>on</strong> procedures) in calculati<strong>on</strong> structure.<br />
Inventory database c<strong>on</strong>tains approx 90 standard material items of technological equipment (pipes, valves, tanks etc.),<br />
approx 50 specific items (pieces, planked comp<strong>on</strong>ents etc.). <str<strong>on</strong>g>The</str<strong>on</strong>g> inventory database also c<strong>on</strong>tains 14 building categories<br />
(mas<strong>on</strong>ry, c<strong>on</strong>crete, steel c<strong>on</strong>structi<strong>on</strong> etc.). A new task is costing the larger technological aggregates decommissi<strong>on</strong>ing<br />
in nuclear power plants. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper introduces development of larger technological aggregates inventory database. <str<strong>on</strong>g>The</str<strong>on</strong>g>se<br />
aggregates include: 1. Reactor and its internals 2. Steam generator 3. Pressurizer 4. Refueling machine, etc.. Larger<br />
technological aggregates decommissi<strong>on</strong>ing activities need to be implemented into decommissi<strong>on</strong>ing planning and costing<br />
Code OMEGA. So decommissi<strong>on</strong>ing procedures representing these activities have to be developed for technological<br />
aggregates, and dismantling unit factors need to be set up as well. A proper definiti<strong>on</strong> of dismantling techniques and<br />
workgroups performing the techniques is also important, taking into account presence of activated and c<strong>on</strong>taminated<br />
materials to be dismantled. Where a dose rate is higher than a limit for manual dismantling, remote dismantling<br />
techniques are applied. Paper introduces manual and remote techniques available for larger technological aggregates<br />
dismantling. Dismantling procedures of larger technological aggregates are based <strong>on</strong> reversed sequence of their<br />
commissi<strong>on</strong>ing. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper also deals with specific dismantling procedures, when equipment is dismantled as a whole and<br />
moved to a fragmentati<strong>on</strong> facility. <str<strong>on</strong>g>The</str<strong>on</strong>g>re it will be fragmented to smaller parts, put into c<strong>on</strong>tainers for disposal in<br />
radioactive waste repository. Decommissi<strong>on</strong>ing of larger technological aggregates relates to buildings where aggregates<br />
are housed in and the paper also deals with their demoliti<strong>on</strong>.<br />
5) 40190 – Dismantling Method of Fuel Cycle Facilities Obtained by Dismantling of the JRTF<br />
Fumihiko Kanayama, JAEA (Japan)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> Japan Atomic Energy Research Institute Reprocessing Test Facility (JRTF) was the first reprocessing facility<br />
which was c<strong>on</strong>structed by applying <strong>on</strong>ly Japanese technology to establish basic technology <strong>on</strong> wet reprocessing. JRTF<br />
had been operated since 1968 to 1969 using spent fuels (uranium metal / aluminum clad, about 600kg as uranium metal<br />
and 600MWD/T) from the Japan Research Reactor No.3 (JRR-3). Reprocessing testings <strong>on</strong> PUREX process were<br />
implemented at 3 runs, so that, 200g of plut<strong>on</strong>ium dioxide were extracted. After JRTF was shut down at 1970, it had been<br />
used for research and development of reprocessing since 1971. <str<strong>on</strong>g>The</str<strong>on</strong>g> more mature research and development of nuclear are,<br />
the more opportunity of dismantling of old nuclear facilities would be. JAEA has an experience of full scale of<br />
dismantling through decommissi<strong>on</strong>ing of JPDR. On the other hand, we didn’t have that of fuel cycle facility. Moreover,<br />
it is c<strong>on</strong>sidered that dismantling methods of nuclear reactor and fuel cycle facility are different for following reas<strong>on</strong>,<br />
comp<strong>on</strong>ents c<strong>on</strong>taminated TRU nuclide including Pu, c<strong>on</strong>taminati<strong>on</strong> form being many kinds, and comp<strong>on</strong>ents installed<br />
inside narrow cells. Dismantling methods are important factor to decide manpower and time for dismantling. So, it is<br />
indispensable to optimize dismantling method in order to minimize manpower and time for dismantling. C<strong>on</strong>sidering the<br />
background menti<strong>on</strong>ed above, the decommissi<strong>on</strong>ing project of JRTF was started in 1990. <str<strong>on</strong>g>The</str<strong>on</strong>g> decommissi<strong>on</strong>ing project<br />
of JRTF is carrying out phase by phase. Phase 1; Investigati<strong>on</strong> for dismantling of the JRTF. Phase 2; R&D of<br />
decommissi<strong>on</strong>ing technologies for dismantling of the JRTF. Phase 3; Actual dismantling of the JRTF. <str<strong>on</strong>g>The</str<strong>on</strong>g>re were several<br />
comp<strong>on</strong>ents used for reprocessing and a system for liquid radwaste storage, and those were installed inside of each of<br />
several thick c<strong>on</strong>crete cells. <str<strong>on</strong>g>The</str<strong>on</strong>g> inner surfaces of each cell were c<strong>on</strong>taminated by TRU nuclides including Pu. In phase 3,<br />
comp<strong>on</strong>ents used in reprocessing and a system for liquid radwaste storage were dismantled. Moreover, c<strong>on</strong>crete walls<br />
(including ceiling) were opened to make entrances in this work. Effective practices for dismantling fuel cycle facilities<br />
were obtained through these works. On this report, I introduce effective dismantle method obtained by actual dismantling<br />
activities in JRTF.<br />
6) 40191 – Computer Simulati<strong>on</strong> of Cryogenic Jet Cutting for Dismantling Highly Activated Facilities<br />
Sung-Kyun Kim, Kune-Woo Lee, KAERI (Korea Rep.)<br />
Cryogenic cutting technology is <strong>on</strong>e of the most suitable technologies for dismantling nuclear facilities due to the<br />
fact that a sec<strong>on</strong>dary waste is not generated during the cutting process. In this paper the feasibility of cryogenic cutting<br />
technology has been investigated by using a computer simulati<strong>on</strong>. In the computer simulati<strong>on</strong>, a hybrid method combined<br />
with the SPH (smoothed particle hydrodynamics) method and with the FE (finite element) method was used. And also, a<br />
penetrati<strong>on</strong> depth equati<strong>on</strong>, for the design of the cryogenic cutting system, was used and the design variables and<br />
operati<strong>on</strong> c<strong>on</strong>diti<strong>on</strong>s to cut a 10 mm thickness for steel were determined. Finally the main comp<strong>on</strong>ents of the cryogenic<br />
cutting system were developed <strong>on</strong> the basis of the obtained design values.<br />
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Abstracts<br />
7) 40193 – Strippable Core-shell Polymer Emulsi<strong>on</strong> for Dec<strong>on</strong>taminati<strong>on</strong> of Radioactive Surface C<strong>on</strong>taminati<strong>on</strong><br />
Bum-Kyoung Seo, Bum-Kyoung Seo, Kune-Woo Lee, KAERI (Korea Rep.)<br />
Strippable coatings are innovative technologies for dec<strong>on</strong>taminati<strong>on</strong> that effectively reduce loose c<strong>on</strong>taminati<strong>on</strong>.<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g>se coatings are polymer mixtures, such as water-based organic polymers that are applied to a surface by paintbrush,<br />
roller or spray applicator. In this study, the core-shell composite polymer for dec<strong>on</strong>taminati<strong>on</strong> from the surface<br />
c<strong>on</strong>taminati<strong>on</strong> was synthesized by the method of emulsi<strong>on</strong> polymerizati<strong>on</strong> and blends of polymers. <str<strong>on</strong>g>The</str<strong>on</strong>g> strippable<br />
polymer emulsi<strong>on</strong> is composed of the poly(styrene-ethyl acrylate) [poly(St-EA)] composite polymer, poly(vinyl alcohol)<br />
(PVA) and polyvinylpyrrolid<strong>on</strong>e (PVP). <str<strong>on</strong>g>The</str<strong>on</strong>g> morphology of the composite emulsi<strong>on</strong> particle was core-shell structure,<br />
with polystyrene (PS) as the core and poly(ethyl acrylate) (PEA) as the shell. Core-shell polymers of styrene (St)/ethyl<br />
acrylate (EA) pair were prepared by sequential emulsi<strong>on</strong> polymerizati<strong>on</strong> in the presence of sodium dodecyl sulfate (SDS)<br />
as an emulsifier using amm<strong>on</strong>ium persulfate (APS) as an initiator. Related tests and analysis c<strong>on</strong>firmed the success in<br />
synthesis of composite polymer. <str<strong>on</strong>g>The</str<strong>on</strong>g> products are characterized by FT-IR spectroscopy, TGA that were used,<br />
respectively, to show the structure, the thermal stability of the prepared polymer. Two-phase particles with a core-shell<br />
structure were obtained in experiments where the estimated glass transiti<strong>on</strong> temperature and the morphologies of<br />
emulsi<strong>on</strong> particles. Dec<strong>on</strong>taminati<strong>on</strong> factors (DF) of the strippable polymeric emulsi<strong>on</strong> were evaluated with the polymer<br />
blend c<strong>on</strong>tents. <str<strong>on</strong>g>The</str<strong>on</strong>g> dec<strong>on</strong>taminati<strong>on</strong> factors obtained for Sr-90 <strong>on</strong> the disk plate studies were observed the DF values of<br />
8.9 to 12.8 at all the polymer compositi<strong>on</strong>.<br />
SESSION R4: ER Poster<br />
1) 40025 – Improvement of quicklime mixing treatment by carb<strong>on</strong> dioxide ventilati<strong>on</strong><br />
Yuki Nakagawa, Hisayoshi Hashimoto, Hitachi C<strong>on</strong>structi<strong>on</strong> Machinery Co., Ltd. (Japan);<br />
Koichi Suto, Chihiro Inoue, Tohoku University ( Japan)<br />
This report describes fundamental examinati<strong>on</strong> about a quicklime mixing treatment combined with carb<strong>on</strong> dioxide<br />
ventilati<strong>on</strong> for the remediati<strong>on</strong> process of soils polluted with volatile organic compounds (VOCs). <str<strong>on</strong>g>The</str<strong>on</strong>g> quicklime mixing<br />
treatment is widely applied to remove volatile pollutants in soils using 65.17 kJ/mol of the heat from the following<br />
reacti<strong>on</strong>; CaO+H2O?Ca(OH)2?? To keep higher temperature and to ensure most of VOCs are volatilized, 10 % of<br />
calcium oxide is usually mixed with soils in this treatment. However, much amount of additi<strong>on</strong> of calcium oxide results<br />
in higher alkaline soil pH and gives serious damage to the soil ecosystems. To solve this problem, a simultaneous<br />
ventilati<strong>on</strong> of carb<strong>on</strong> dioxide during calcium oxide mixing to polluted soil was c<strong>on</strong>ducted. <str<strong>on</strong>g>The</str<strong>on</strong>g> formati<strong>on</strong> of calcium<br />
carb<strong>on</strong>ate according to following reacti<strong>on</strong> produces 92.84 kJ/mol of the heat; Ca(OH)2+H2CO3? CaCO3+2H2O?? It is<br />
expected that the heat from the above reacti<strong>on</strong> can be used for the treatment and the amount of calcium oxide additi<strong>on</strong> for<br />
the treatment can be reduced. Laboratory experiments showed that more than half of calcium oxide changed to calcium<br />
carb<strong>on</strong>ate when carb<strong>on</strong> dioxide ventilated to the mixed soil sample after 5% of calcium oxide and 5% of water mixed<br />
with the soil. Maximum soil temperature for this treatment increased same as that for the treatment with 10% calcium<br />
oxide. Pilot level and operati<strong>on</strong>al level experiments c<strong>on</strong>firmed the effectiveness of the simultaneous ventilati<strong>on</strong> of carb<strong>on</strong><br />
dioxide during the quicklime mixing process.<br />
2) 40166 – Procedure and result of decommissi<strong>on</strong> of R&D facility of Uranium fuel<br />
Hirokazu Tanaka, Masao Shimizu, Ryoji Tanimoto, Kazuhiko Maekawa,<br />
Shinzo Ueta, Mitsubishi Materials Corporati<strong>on</strong> (Japan); Susumu Tojo, SERNUC Corporati<strong>on</strong> (Japan)<br />
Mitsubishi Materials Corporati<strong>on</strong> (MMC) had carried out nuclear engineering researches and developments such as<br />
Uranium fuel development since 1954 in MMC’s research laboratory in Omiya city in Japan. <str<strong>on</strong>g>The</str<strong>on</strong>g> facilities of the<br />
laboratory had been decommissi<strong>on</strong>ed since 1998 to 2005. <str<strong>on</strong>g>The</str<strong>on</strong>g> research activities were transferred to the new research<br />
laboratories established in different locati<strong>on</strong>. At the time of the decommissi<strong>on</strong> work, there was no suitable law restricti<strong>on</strong><br />
to distinguish the dec<strong>on</strong>taminated waste as radioactive or not. MMC discussed and adopted the pragmatic procedure<br />
under its own resp<strong>on</strong>sibility with c<strong>on</strong>sultati<strong>on</strong> of regulatory authority and technical authority outside the company. <str<strong>on</strong>g>The</str<strong>on</strong>g><br />
decommissi<strong>on</strong>ed material could be divided into two categories. One was research apparatus and building. Another was<br />
shallow rand soil c<strong>on</strong>tacted to the facility. Metal wastes were mainly rose from the apparatus. Metal, c<strong>on</strong>crete, and wood<br />
wastes were rose from building. At first, these wastes were dec<strong>on</strong>taminated for example by blasting. <str<strong>on</strong>g>The</str<strong>on</strong>g>n the surface<br />
radioactivity was measured mainly by GM-survey meter and temporally by alpha-survey meter to compare the<br />
radioactivity criteria. In this case, the radioactivity criteria was decided as the natural radioactivity measured outside the<br />
facility without any influence of artificial radioactivity. Natural radioactivity varies within a certain range, therefore it<br />
was measured and treated statistically. Radioactivity of the soils c<strong>on</strong>tacted to the facility were measured because there<br />
was possibility that small amount c<strong>on</strong>taminated liquid had flew out from the facility through the crack of pipes and<br />
fracture in basement c<strong>on</strong>crete. It was very difficult to decide whether the soil was c<strong>on</strong>taminated or not, because the soil<br />
naturally c<strong>on</strong>tains radioactive nuclides as U-238, Th-232, K-40, etc. Soil from ten areas in the city far away from the<br />
laboratory were collected and analyzed its radioactivity by the automatic alpha-beta counting system c<strong>on</strong>sisted of a<br />
ZnS(Ag) scintillati<strong>on</strong> detector and a plastic scintillati<strong>on</strong> detector. <str<strong>on</strong>g>The</str<strong>on</strong>g> analyzed data were treated statistically to decide<br />
115
Abstracts<br />
the appropriate value of natural radioactivity. <str<strong>on</strong>g>The</str<strong>on</strong>g> law <strong>on</strong> decommissi<strong>on</strong> work was established later, however there is still<br />
no suitable quantitative criteria to distinguish uranium c<strong>on</strong>taminated material or not. MMC’s criteria was c<strong>on</strong>sidered as<br />
very low, which was close to natural radioactivity. In other words, the facility was decommissi<strong>on</strong>ed under very safely<br />
manner. <str<strong>on</strong>g>The</str<strong>on</strong>g> wastes generated from the decommissi<strong>on</strong> work are being held in storehouse build in the same area.<br />
3) 40210 – Photo-Catalytic Degradati<strong>on</strong> of Industrial Pollutant by Using Nano-technology and Solar energy in<br />
the Eastern Area of Kingdom of Saudi Arabia<br />
Osama S.Y. Mohamed, Abdullah A. Al Jaafari, King Faisal University (Saudi Arabia)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> nano-material is <strong>on</strong>e of the most dynamic and fastest growing areas of research in the fields of science,<br />
engineering, and medicine. Also, in Saudi Arabia, the sun light is available in all year. In the same time, Marine and fresh<br />
waters can be c<strong>on</strong>sidered, at present, to c<strong>on</strong>sist of a complex mixture of dissolved and n<strong>on</strong> dissolved organic materials as<br />
well as biological substrates and colloidal aggregates. Following this line, we prepared nano-particles of zinc oxide inside<br />
Pressurized vessel with temperature c<strong>on</strong>troller unit and dried under supercritical c<strong>on</strong>diti<strong>on</strong>s in presence of ethanol. <str<strong>on</strong>g>The</str<strong>on</strong>g>se<br />
nanoparticles have used as photocatalyst in order to destroy colored dye pollutant (Acid green 1) in the presence of sun<br />
light. In the same trend, we developed zinc oxide nano-particles by doping with aluminum oxide in order to increase the<br />
efficiency of its visible photo-catalytic activity. <str<strong>on</strong>g>The</str<strong>on</strong>g> experimental results showed that the doped and undoped zinc oxide<br />
nanoparticles are very active for catalytic degradati<strong>on</strong>s of pollutants in presence of sun light.<br />
4) 40224 – Hydrogen Producti<strong>on</strong> from a PV/PEM Electrolyzer System Using a Neural-Network-Based MPPT<br />
Algorithm<br />
Abd El-Shafy Nafeh, Electr<strong>on</strong>ics Research Institute (Egypt)<br />
<str<strong>on</strong>g>The</str<strong>on</strong>g> electrolysis of water using a polymer electrolyte membrane (PEM) electrolyzer is a very vital and efficient<br />
method of producing hydrogen (H2). <str<strong>on</strong>g>The</str<strong>on</strong>g> performance of this method can be significantly improved if a photovoltaic<br />
(PV) array, with maximum-power-point (MPP) tracker, is utilized as an energy source for the electrolyzer. This paper<br />
suggests a stand-al<strong>on</strong>e PV/PEM electrolyzer system to produce pure hydrogen. <str<strong>on</strong>g>The</str<strong>on</strong>g> paper also develops the different<br />
mathematical models for each c<strong>on</strong>stituent subsystem. Moreover, the paper develops the suitable maximum-power-point<br />
tracking algorithm that is based up<strong>on</strong> utilizing the neural network. This algorithm is utilized together with the acti<strong>on</strong> of<br />
the PI c<strong>on</strong>troller to improve the performance of the suggested stand-al<strong>on</strong>e PV/PEM electrolyzer system through<br />
maximizing the hydrogen producti<strong>on</strong> rate for every instant. Finally, the suggested hydrogen producti<strong>on</strong> system is<br />
simulated using the Matlab/Simulink and neural network toolbox. <str<strong>on</strong>g>The</str<strong>on</strong>g> simulati<strong>on</strong> results of the system indicate the<br />
improved relative performance of the suggested hydrogen producti<strong>on</strong> system compared with the traditi<strong>on</strong>al case of direct<br />
c<strong>on</strong>necti<strong>on</strong> between the PV array and the PEM electrolyzer.<br />
5) 40301 – Cement based solidificati<strong>on</strong> / stabilizati<strong>on</strong> of industrial c<strong>on</strong>taminated soil using various cement<br />
additives<br />
Grega E. Voglar, RDA (Slovenia); D. Lestan, Agr<strong>on</strong>omy Department, Biotechnical Faculty,<br />
University of Ljubljana, (Slovenia)<br />
A large number of industrial activities produce wastes and c<strong>on</strong>taminants that reach the soil through direct disposal,<br />
emissi<strong>on</strong>s, spills, leaks and other pathways. An increasing number of aband<strong>on</strong>ed industrial sites (brownfields) have<br />
emerged as a result of weak envir<strong>on</strong>mental regulati<strong>on</strong> over decades. Soil clean-up operati<strong>on</strong>s (remediati<strong>on</strong>s) of<br />
brownfields, followed by redevelopment is essential to lower the urbanizati<strong>on</strong> pressure <strong>on</strong> arable and other farmland<br />
(greenfields). <str<strong>on</strong>g>The</str<strong>on</strong>g> town of Celje in central Slovenia has a l<strong>on</strong>g traditi<strong>on</strong> of metallurgical and chemical industries, which<br />
started in 1874 with a zinc smelter and was subsequently expanded to the producti<strong>on</strong> of Zn and Pb oxides and Ba salts. In<br />
1912, the synthesis of H2SO4 and in 1970 the producti<strong>on</strong> of TiO2 started. Obsolete manufacturing plants have gradually<br />
been closed and replaced with new <strong>on</strong>es in a new locati<strong>on</strong>. <str<strong>on</strong>g>The</str<strong>on</strong>g> whole industrial site of “old Cinkarna” was finally<br />
demolished in 2003, leaving a brownfield area of some 170,000 m2 very close to the city centre and with highly<br />
c<strong>on</strong>taminated soils, primarily with potentially toxic metals and metaloides (PTMs) and to some extend also with organic<br />
pollutants. In a laboratory study, 15% (w/w) of ordinary portland cement (OPC), black portland cement (BPC) and<br />
puculanic cement (PC) combined with various cement additives were used for solidificati<strong>on</strong> / stabilizati<strong>on</strong> (S/S) of Cd,<br />
Pb, Zn, Cu, Ni and As c<strong>on</strong>taminated soils from the former industrial site. Soils formed solid m<strong>on</strong>oliths with all cements.<br />
S/S effectiveness was assessed by measuring the mechanical strength of the m<strong>on</strong>oliths, c<strong>on</strong>centrati<strong>on</strong>s of metals in<br />
dei<strong>on</strong>ised water and TCLP (Toxicity Characteristic Leaching Procedure) soil extracts, and mass transfer of metals.<br />
C<strong>on</strong>centrati<strong>on</strong>s of Cd, Pb, Zn and Ni in water extracts from S/S soils generally decreased, while c<strong>on</strong>centrati<strong>on</strong>s of As and<br />
Cu increased. C<strong>on</strong>centrati<strong>on</strong>s of Cd, Pb, Zn, Cu and Ni in the TCLP extracts from S/S soils were lower than from original<br />
soils, while the extractability of As from S/S soils increased. Overall, the c<strong>on</strong>centrati<strong>on</strong> of metals in dei<strong>on</strong>ised water and<br />
TCLP soluti<strong>on</strong>, obtained after extracti<strong>on</strong> of the S/S soils, was below the regulatory limits. S/S greatly reduced the mass<br />
transfer of Cd (up to 300-times), Pb (up to 53.7-times) and Zn (up to 3843-times). Mass transfer of Ni was generally also<br />
reduced, while that of Cu and As increased in some S/S soils. Based <strong>on</strong> the findings of mass-transfer mechanism analysis<br />
the predominant mechanism of release was surface wash-off of metals otherwise physically encapsulated within the<br />
cementous soil matrix.<br />
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Abstracts<br />
SESSION M3: EM/PI Poster<br />
1) 40099 – Removal of Fluorine and Bor<strong>on</strong> from Groundwater Using Radiati<strong>on</strong>-induced Graft Polymerizati<strong>on</strong><br />
Adsorbent at Mizunami Underground Research Laboratory<br />
Yosuke Iyatomi, Hiroyuki Hoshina, Noriaki Seko, Noboru Kasai, Yuji Ueki, Masao Tamada, JAEA (Japan)<br />
High fluorine and bor<strong>on</strong> c<strong>on</strong>tents in groundwater are comm<strong>on</strong>ly reduced using coagulati<strong>on</strong> and i<strong>on</strong>-exchange<br />
treatments. As an alternative, we tested the efficiency of fluorine and bor<strong>on</strong> removal from groundwater using<br />
radiati<strong>on</strong>induced graft polymerizati<strong>on</strong> adsorbent. <str<strong>on</strong>g>The</str<strong>on</strong>g> durability of the adsorbent was also determined by varying<br />
groundwater flowthrough rates and repetitive use of the adsorbent. <str<strong>on</strong>g>The</str<strong>on</strong>g> results indicated that it was possible for the<br />
adsorbent to remove more than 95% of bor<strong>on</strong> and fluorine from the groundwater, and that the performance of the<br />
adsorbent for bor<strong>on</strong> removal was better than comm<strong>on</strong>ly used i<strong>on</strong>-exchange resin. <str<strong>on</strong>g>The</str<strong>on</strong>g> adsorbent used several times was<br />
able to remove bor<strong>on</strong>, indicating that the adsorbent can be used for efficient bor<strong>on</strong> removal.<br />
2) 40184 – <str<strong>on</strong>g>The</str<strong>on</strong>g> Optimized Risk Management of the Waste from NORM and Nuclear Industries - How to<br />
Harm<strong>on</strong>ize Risk from Various Sources<br />
Yoko Fujikawa, Kyoto University Research Reactor Institute (Japan);<br />
Michikuni Shimo, Fujita Health University (Japan);<br />
Hidenori Y<strong>on</strong>ehara, Nati<strong>on</strong>al Instuitute of Radiological Sciences (Japan);<br />
Tadashi Tujimoto, Electr<strong>on</strong> Science Institute (Japan)<br />
We compared the existing regulati<strong>on</strong> <strong>on</strong> management of radioactive and n<strong>on</strong>-radioactive wastes with the ideal<br />
legislati<strong>on</strong> procedures for protecti<strong>on</strong> of envir<strong>on</strong>ment. <str<strong>on</strong>g>The</str<strong>on</strong>g> comparis<strong>on</strong> revealed the necessity of risk-based regulati<strong>on</strong>,<br />
c<strong>on</strong>siderati<strong>on</strong> for ethics and cost-effectiveness of the regulati<strong>on</strong>, and optimal usage of regulati<strong>on</strong> resources. In order to<br />
assess the cost-effectiveness of several different waste disposal opti<strong>on</strong>s, the c<strong>on</strong>cept of disposal cost per unit radiotoxicity<br />
(mSv or m3) in waste (CPR hereafter) was introduced and calculated. <str<strong>on</strong>g>The</str<strong>on</strong>g> results revealed that current disposal opti<strong>on</strong> of<br />
high level radioactive waste (underground burial) was more cost-effective than that of TENORM and asbestos c<strong>on</strong>taining<br />
waste.<br />
3) 40205 – Exposure Dose Evaluati<strong>on</strong> of Worker at Radioactive Waste Incinerati<strong>on</strong> Facility <strong>on</strong> KEARI<br />
Sang Kyu Park, J<strong>on</strong>g Se<strong>on</strong> Je<strong>on</strong>, Younhwa Kim, Jaemin Lee, NESYS.CO., LTD. (Korea Rep.);<br />
Ki W<strong>on</strong> Lee, KAERI, (Korea Rep.)<br />
In this study, we evaluate the exposure dose of worker by operating at radioactive waste incinerati<strong>on</strong> facility that is<br />
in KAERI(Korea Atomic Energy Research Institute) for safety analysis. <str<strong>on</strong>g>The</str<strong>on</strong>g> incinerati<strong>on</strong> facility that is areas are 570 ?,<br />
annual treatment quantities are 40,000 kg is separated with radiati<strong>on</strong> z<strong>on</strong>e and n<strong>on</strong>-radiati<strong>on</strong> area to installed extra<br />
equipment for incinerati<strong>on</strong> process. <str<strong>on</strong>g>The</str<strong>on</strong>g> incinerati<strong>on</strong> facility c<strong>on</strong>sist of preparing system, incinerati<strong>on</strong> processing system,<br />
exhaust gas treatment system, ash treatment system and c<strong>on</strong>trolled with measurement. Radioactive waste incinerati<strong>on</strong><br />
facility during normal operati<strong>on</strong>, worker is exposured radiati<strong>on</strong> by the exposure route of external and internal. <str<strong>on</strong>g>The</str<strong>on</strong>g>y are<br />
exposured by external radiati<strong>on</strong> that was effected by treated waste material and characteristic. In case of internal exposure,<br />
it is primary fact that is inhalati<strong>on</strong> of c<strong>on</strong>taminated air. <str<strong>on</strong>g>The</str<strong>on</strong>g> evaluati<strong>on</strong> assumpti<strong>on</strong> is the next: One is that internal<br />
exposure is c<strong>on</strong>centrati<strong>on</strong> of radioactive material release basis and work is 200 days per year(8 hr per day) because of the<br />
incinerati<strong>on</strong> facility is operated and managed in critical regulati<strong>on</strong> under maximum acceptance air c<strong>on</strong>taminati<strong>on</strong>. Result<br />
of evaluati<strong>on</strong>, maximum exposure dose is 3.07 mSy/y and internal exposure dose is 2.5 mSy/yr according as selecting the<br />
treated radioacitve waste. <str<strong>on</strong>g>The</str<strong>on</strong>g> exposure dose of assessment result is lower the basis of domestic nuclear law and<br />
regulati<strong>on</strong> limit in IAEA.<br />
4) 40209 – Scenario Development for Safety Assessment of Waste Repository for Feasibility Study <strong>on</strong><br />
Transmutati<strong>on</strong> of Spent Nuclear Fuel into LILW using PEACER<br />
Sung-yeop Kim, Kun Jai Lee, KAIST (Korea Rep.)<br />
Safety assessment of radioactive waste repository is necessary for feasibility study <strong>on</strong> transmutati<strong>on</strong> of spent nuclear<br />
fuel into LILW(Low and Intermediate Level Waste) using transmutati<strong>on</strong> reactor PEACER(Proliferati<strong>on</strong>-resistant,<br />
Envir<strong>on</strong>mental-friendly, Accident-tolerant, C<strong>on</strong>tinuable-energy and Ec<strong>on</strong>omical Reactor). PEACER is a c<strong>on</strong>ceptual<br />
liquid metal fast reactor using Pb-Bi as a coolant. Scenario development is important to the safety assessment for several<br />
reas<strong>on</strong>s. Scenarios provide the c<strong>on</strong>text in which safety assessments are performed. Scenarios influence model<br />
development and data collecti<strong>on</strong> efforts. <str<strong>on</strong>g>The</str<strong>on</strong>g>y have become a very important aspect of c<strong>on</strong>fidence building for the<br />
post-closure safety assessment. In this study, c<strong>on</strong>diti<strong>on</strong> of medium depth disposal about 100-200m in granite is<br />
c<strong>on</strong>sidered. Waste from PWR and PEACER c<strong>on</strong>sidering DF(Dec<strong>on</strong>taminati<strong>on</strong> Factor) is disposed in this c<strong>on</strong>diti<strong>on</strong>.<br />
Scenario for these c<strong>on</strong>cepts are established by screening FEP(Feature, Event, Process) database and benchmarking<br />
reference safety assessment report.<br />
117
List of Pre-Registrants<br />
Kapila FERNANDO Australian Nuclear Science and Technology Organisati<strong>on</strong> Australia<br />
Lynn TAN Australian Nuclear Science and Technology Organisati<strong>on</strong> Australia<br />
Robin George HEARD IAEA Austria<br />
Irena MELE IAEA Austria<br />
Roman BEYERKNECHT Nuclear Engineering Seibersdorf GmbH Austria<br />
Wolfgang STUDECKER Nuclear Engineering Seibersdorf GmbH Austria<br />
Jan DECKERS Belgoprocess Belgium<br />
Henri VANBRABANT Belgoprocess Belgium<br />
Paul LUYCX Castor C<strong>on</strong>sulting Belgium<br />
Lou AREIAS SCK.CEN Belgium<br />
Alain VAN COTTHEM Technum-Tractebel Engineering Nv Belgium<br />
Joseph, Ghislain BOUCAU Westinghouse Belgium<br />
Sheila M. BROOKS Atomic Energy of Canada Limited Canada<br />
Miklos GARAMSZEGHY Nuclear Waste Management Organizati<strong>on</strong> Canada<br />
Josef PODLAHA Nuclear Research Institute Rez plc Czech Rep.<br />
Frantisek SVITAK Nuclear Research Institute Rez Czech Rep.<br />
Karel SVOBODA Nuclear Research Institute Rez, Czech Republic Czech Rep.<br />
Eduard Josef HANSLÍK T. G. Masaryk Water Research Institute Czech Rep.<br />
Gérald OUZOUNIAN ANDRA France<br />
Jean-Guy NOKHAMZON Commissariat à l'énergie atomique France<br />
Claudio PESCATORE OECD/NEA France<br />
Florence GASSOT-GUILBERT SGN AREVA GROUP France<br />
Peter PILLOKAT AREVA NP GmbH Germany<br />
Christoph Michael STIEPANI AREVA NP GmbH Germany<br />
Johannes FACHINGER Furnaces Nuclear Applicati<strong>on</strong>s Grenoble Germany<br />
Markus Adam HARTUNG NUKEM Technologies GmbH Germany<br />
Jörg WÖRNER RD-Hanau Germany<br />
Katharina AYMANNS Research Centre Juelich Germany<br />
Natalia GIRKE Research Centre Juelich Germany<br />
Hans-Juergen STEINMETZ Research Centre Juelich Germany<br />
Yasuo TOMISHIMA AIST Japan<br />
Motoi KAWANISHI Central Research Institute of Electric Power Industry Japan<br />
Koji NAGANO Central Research Institute of Electric Power Industry Japan<br />
Yukihisa TANAKA Central Research Institute of Electric Power Industry Japan<br />
Masaki TSUKAMOTO Central Research Institute of Electric Power Industry Japan<br />
Yoshifusa FUKUOKA Chubu Electric Power Co., Inc. Japan<br />
Masato WATANABE Chubu Electric Power Co., Inc. Japan<br />
Yoshio KIMURA Chuden CTI Co.,LTD. Japan<br />
Shinichi HOSOYA DIA C<strong>on</strong>sultants Co., Ltd Japan<br />
Miyoshi YOSHIMURA DIA C<strong>on</strong>sultants Co., Ltd. Japan<br />
Chikao Chuck MIYAMOTO EPRI <str<strong>on</strong>g>Internati<strong>on</strong>al</str<strong>on</strong>g> Japan<br />
Masaaki NAKANO Fuji Electric Holdings Co., Ltd. Japan<br />
Gen-Ichi KATAGIRI Fuji Electric Systems Co., Ltd. Japan<br />
Kiyoshi AMEMIYA Hazama Corporati<strong>on</strong> Japan<br />
Yuki NAKAGAWA Hitachi C<strong>on</strong>structi<strong>on</strong> Machinery Co., Ltd. Japan<br />
Hirokazu MINATO Hitachi-GE Nuclear Energy Ltd. Japan<br />
Susumu KAWAKAMI IHI Corporati<strong>on</strong> Japan<br />
Hirofumi TSUKADA Institute for Envir<strong>on</strong>mental Sciences Japan<br />
Takeshi ISHIKURA Institute of Applied Energy Japan<br />
Hir<strong>on</strong>obu ABE Japan Atomic Energy Agency Japan<br />
Ippei AMAMOTO Japan Atomic Energy Agency Japan<br />
Kenji AMANO Japan Atomic Energy Agency Japan<br />
Daisuke AOSAI Japan Atomic Energy Agency Japan<br />
Shiho ASAI Japan Atomic Energy Agency Japan<br />
Shuji DAIMARU Japan Atomic Energy Agency Japan<br />
Takahiro HANAMURO Japan Atomic Energy Agency Japan<br />
Kazumasa HIOKI Japan Atomic Energy Agency Japan<br />
118
Sohei IKEGAMI Japan Atomic Energy Agency Japan<br />
Ken-Ichiro ISHIMORI Japan Atomic Energy Agency Japan<br />
Yuu ISHIMORI Japan Atomic Energy Agency Japan<br />
Yosuke IYATOMI Japan Atomic Energy Agency Japan<br />
Gento KAMEI Japan Atomic Energy Agency Japan<br />
Fumihiko KANAYAMA Japan Atomic Energy Agency Japan<br />
Akira KITAMURA Japan Atomic Energy Agency Japan<br />
Takanori KUNIMARU Japan Atomic Energy Agency Japan<br />
Kensuke KURAHASHI Japan Atomic Energy Agency Japan<br />
Toshikatsu MAEDA Japan Atomic Energy Agency Japan<br />
Keisuke MAEKAWA Japan Atomic Energy Agency Japan<br />
Hitoshi MAKINO Japan Atomic Energy Agency Japan<br />
Toshiyuki MATSUOKA Japan Atomic Energy Agency Japan<br />
Yoshihiro MEGURO Japan Atomic Energy Agency Japan<br />
Kaname MIYAHARA Japan Atomic Energy Agency Japan<br />
Takashi MIZUNO Japan Atomic Energy Agency Japan<br />
Shinichi NAKAYAMA Japan Atomic Energy Agency Japan<br />
Masashi NAKAYAMA Japan Atomic Energy Agency Japan<br />
Tadafumi NIIZATO Japan Atomic Energy Agency Japan<br />
Kunio OTA Japan Atomic Energy Agency Japan<br />
Sidik PERMANA Japan Atomic Energy Agency Japan<br />
Hiromitsu SAEGUSA Japan Atomic Energy Agency Japan<br />
Hiroshi SAITO Japan Atomic Energy Agency Japan<br />
Hiroyuki SANADA Japan Atomic Energy Agency Japan<br />
Eiji SASAO Japan Atomic Energy Agency Japan<br />
Haruo SATO Japan Atomic Energy Agency Japan<br />
Yuji SHIBAHARA Japan Atomic Energy Agency Japan<br />
Seiji TAKEDA Japan Atomic Energy Agency Japan<br />
Shinji TAKEUCHI Japan Atomic Energy Agency Japan<br />
Tadao TANAKA Japan Atomic Energy Agency Japan<br />
Tetsuya TOKIWA Japan Atomic Energy Agency Japan<br />
Hiroyuki UMEKI Japan Atomic Energy Agency Japan<br />
Isao YAMAGISHI Japan Atomic Energy Agency Japan<br />
Yuhei YAMAMOTO Japan Atomic Energy Agency Japan<br />
Satoshi YANAGIHARA Japan Atomic Energy Agency Japan<br />
Hideharu YOKOTA Japan Atomic Energy Agency Japan<br />
Naoki ZAIMA Japan Atomic Energy Agency Japan<br />
Tomohisa ZAITSU Japan Atomic Energy Agency Japan<br />
Tatsujiro SUZUKI Japan Atomic Energy Commissi<strong>on</strong> Japan<br />
Satoshi KARIGOME Japan Atomic Power Company Japan<br />
Ken-Ichi TANAKA Japan Atomic Power Company Japan<br />
Kazuhisa YAMAGUCHI Japan Atomic Power Company Japan<br />
Kazuhiko YAMAMOTO Japan Atomic Power Company Japan<br />
Keizaburou YOSHINO Japan Atomic Power Company Japan<br />
Yukihiro IGUCHI Japan Nuclear Energy Safety Organizati<strong>on</strong> Japan<br />
Masami KATO Japan Nuclear Energy Safety Organizati<strong>on</strong> Japan<br />
Yusuke MASUDA Japan Nuclear Energy Safety Organizati<strong>on</strong> Japan<br />
Mamoru KUMAGAI Japan Nuclear Fuel Limited Japan<br />
Masataka KAMITSUMA Japan NUS Co. Ltd. Japan<br />
Keiji KUSAMA Japan Radioisotope Associati<strong>on</strong> Japan<br />
Takao IKEDA JGC Corporati<strong>on</strong> Japan<br />
Atsushi MUKUNOKI JGC Corporati<strong>on</strong> Japan<br />
Kunihiro NAKAI JGC Corporati<strong>on</strong> Japan<br />
Kiyoshi OYAMADA JGC Corporati<strong>on</strong> Japan<br />
Hajime TAKAO JGC Corporati<strong>on</strong> Japan<br />
Ichizo KOBAYASHI Kajima Corporati<strong>on</strong> Japan<br />
Toshihiko HIGASHI Kansai Electric Power Company Japan<br />
Takashi NISHIO Kobe Steel, Ltd Japan<br />
Yoko FUJIKAWA Kyoto University Japan<br />
Takumi KUBOTA Kyoto University Japan<br />
119
Kenji KOTOH Kyushu University Japan<br />
Takeshi NAKAMURA Kyushu University Japan<br />
Yuzo YAMASHITA Kyushu University Japan<br />
Tadahiro KATSUTA Meiji University Japan<br />
Hirokuni ITO Ministry of Educati<strong>on</strong>, Culture, Sports, Science and Technology Japan<br />
Akira SAKASHITA Mitsubishi Heavy Industries, INC Japan<br />
Hirokazu TANAKA Mitsubishi Materials Corporati<strong>on</strong> Japan<br />
Nakazawa TOSHIYUKI Mitsubishi Materials Corporati<strong>on</strong> Japan<br />
Shinzo UETA Mitsubishi Materials Corporati<strong>on</strong> Japan<br />
Makoto KAWAMURA Mitsubishi Materials Techno Corporati<strong>on</strong> Japan<br />
Uchida SHIGEO Nati<strong>on</strong>al Institute of Radiological Sciences Japan<br />
Keiko TAGAMI Nati<strong>on</strong>al Institute of Radiological Sciences Japan<br />
Yoji KUSAKA NGK Insulators, Ltd. Japan<br />
Hitoshi OHATA NGK Insulators, Ltd. Japan<br />
Katsutoshi TORITA NGK Insulators, Ltd. Japan<br />
Kojuro YAMAMOTO NGK Insulators, Ltd. Japan<br />
Yoshihiko HORIKAWA Nuclear Engineering, Ltd. Japan<br />
Kazuma MIZUKOSHI Nuclear Engineering, Ltd. Japan<br />
Satoru TAKEDA Nuclear Services Company Japan<br />
Shigeki AKAMURA Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Takeshi EBASHI Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Kiyoshi FUJISAKI Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Takahiro GOTO Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Keisuke ISHIDA Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Eiichi ISHII Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Kenichi KAKU Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Tomio KAWATA Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Kazumi KITAYAMA Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Satoru SUZUKI Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Hiroyuki TSUCHI Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Hiroyoshi UEDA Nuclear Waste Management Organizati<strong>on</strong> of Japan Japan<br />
Tatsuya TANAKA Obayashi corporati<strong>on</strong> Japan<br />
Hidekazu ASANO Radioactive Waste Management Funding and Research Center Japan<br />
Naoki FUJII Radioactive Waste Management Funding and Research Center Japan<br />
Takahiro NAKAJIMA Radioactive Waste Management Funding and Research Center Japan<br />
Ario NAKAMURA Radioactive Waste Management Funding and Research Center Japan<br />
Hitoshi NAKASHIMA Radioactive Waste Management Funding and Research Center Japan<br />
Hiromi TANABE Radioactive Waste Management Funding and Research Center Japan<br />
Takahiro YOSHIDA Radioactive Waste Management Funding and Research Center Japan<br />
Mito AKIYOSHI Senshu University Japan<br />
Satohito TOGURI Shimizu corporati<strong>on</strong> Japan<br />
Yuji IJIRI Taisei Corporati<strong>on</strong> Japan<br />
Hitoshi MIMURA Tohoku University Japan<br />
Keisuke SHIRAI Tohoku University Japan<br />
Yu AOKI Tokyo Electric Power Company Japan<br />
Satoru KANEKO Tokyo Electric Power Company Japan<br />
Kazuhiro TAKEI Tokyo Electric Power Company Japan<br />
Masanori ARITOMI Tokyo Institute of Technology Japan<br />
Hiroshige KIKURA Tokyo Institute of Technology Japan<br />
Takatoshi ASADA Toshiba Corporati<strong>on</strong> Japan<br />
Susumu NAITO Toshiba Corporati<strong>on</strong> Japan<br />
Yuki YAHIRO Toshiba Corporati<strong>on</strong> Japan<br />
Koji OKAMATO University of Tokyo Japan<br />
Satoru TANAKA University of Tokyo Japan<br />
J<strong>on</strong>gse<strong>on</strong> JEON Enesys. Co., Korea Rep.<br />
Juyoul KIM FNC Technology Co., Ltd. Korea Rep.<br />
Sukho<strong>on</strong> KIM FNC Technology Co., Ltd. Korea Rep.<br />
D<strong>on</strong>g-Keun CHO Korea Atomic Energy Research Institute Korea Rep.<br />
Young-Y<strong>on</strong>g JI Korea Atomic Energy Research Institute Korea Rep.<br />
Hee Reyoung KIM Korea Atomic Energy Research Institute Korea Rep.<br />
120
Jin-Seop KIM Korea Atomic Energy Research Institute Korea Rep.<br />
Bum-Kyoung SEO Korea Atomic Energy Research Institute Korea Rep.<br />
Gwangmin SUN Korea Atomic Energy Research Institute Korea Rep.<br />
Yun Seog NAM Korea Nuclear Fuel Korea Rep.<br />
Sun-Joung LEE Korea Radioactive Waste Management Corporati<strong>on</strong> Korea Rep.<br />
Jin-Beak PARK Korea Radioactive Waste Management Corporati<strong>on</strong> Korea Rep.<br />
Ho-Taek YOON Korea Radioactive Waste Management Corporati<strong>on</strong> Korea Rep.<br />
Rizwan AHMED Kyung Hee University Korea Rep.<br />
Muzna ASSI Lebanese Atomic Energy Commissi<strong>on</strong>(LAEC) Leban<strong>on</strong><br />
Renate DE VOS Nuclear Research and c<strong>on</strong>sultancy Group Netherlands<br />
Folasade Mulikat LAWAL MULT ENGINEERING Nigeria<br />
Tamara ZHUNUSSOVA Norwegian Radiati<strong>on</strong> Protecti<strong>on</strong> Authority Norway<br />
Khuram SHAHZAD Peace and Development Organizati<strong>on</strong> Pakistan<br />
Mohamed AMR Qatar University Qatar<br />
Gheorghe BARARIU R.A.A.N. - S.I.T.O.N. Romania<br />
Mikhail BOGOD ECOMET-S Russia<br />
Alexander GELBUTOVSKIY ECOMET-S Russia<br />
Alexander KOLPAKOV ECOMET-S Russia<br />
Alexey VOTYAKOV FSUE RosRAO Russia<br />
Sevastyanov STANISLAV Gazprombank Russia<br />
Dmitry V. MARININ Institute of Chemistry FEDRAS Russia<br />
Alexander KOBELEV Scientific and Industrial Associati<strong>on</strong> RADON Russia<br />
Vladimir DANISKA DECOM, a.s. Slovakia<br />
Peter BEZAK DECONTA, a.s. Slovakia<br />
Frantisek ONDRA DECONTA, a.s. Slovakia<br />
Marek VASKO DECONTA, a.s. Slovakia<br />
Grega E. VOGLAR Regi<strong>on</strong>al Development Agency Celje /University of Ljubljana Slovenia<br />
Helena DANISKOVA Grammar School of St. Michael the Archangel in Piestany Slovakia<br />
Tomas HRNCIR Slovak University of Technology Slovakia<br />
Matej ZACHAR Slovak University of Technology Slovakia<br />
Vladimir NECAS Slovak University of Technology in Bratislava Slovakia<br />
Michal PANIK Slovak University of Technology in Bratislava Slovakia<br />
Kamil KRAVARIK VUJE, Inc. Slovakia<br />
Gerhardus R LIEBENBERG South African Nuclear Energy Corporati<strong>on</strong> (Necsa) South Africa<br />
Lara DURO Amphos 21 Spain<br />
Johan ANDERSSON JA Streamflow AB Sweden<br />
Gunnar HEDIN Westinghouse Sweden<br />
Ian Gerard MCKINLEY McKinley C<strong>on</strong>sulting Switzerland<br />
Irina GAUS Nagra Switzerland<br />
Sven-Peter TEODORI Nagra Switzerland<br />
Stratis VOMVORIS Nagra Switzerland<br />
Dorothea SCHUMANN Paul Scherrer Institute Switzerland<br />
Walter M. HEEP ZWILAG INTERIM STORAGE Switzerland<br />
Chun-Ping JEN Nati<strong>on</strong>al Chung Cheng University Taiwan<br />
F<strong>on</strong>g-In CHOU Nati<strong>on</strong>al Tsing Hua University Taiwan<br />
Chia Chin LI Nati<strong>on</strong>al Tsing Hua University Taiwan<br />
Chih Tien LIU Atomic Energy Council Taiwan<br />
Oleksandr NOVIKOV Chernobyl NPP Ukraine<br />
Ellie SCOURSE Atkins UK<br />
Ricahrd Peter SHAW British Geological Survey UK<br />
Alan SIMPSON Pajarito Scientific Corporati<strong>on</strong> UK<br />
Henry O'GRADY Pars<strong>on</strong>s Brinckerhoff UK<br />
Anibal L. TABOAS Arg<strong>on</strong>ne Nati<strong>on</strong>al Laboratory USA<br />
David Walter JAMES DW James C<strong>on</strong>sulting, LLC USA<br />
Sean Paul BUSHART Electric Power Research Institute USA<br />
Karen KIM Electric Power Research Institute USA<br />
Kenzi KARASAKI Lawrence Berkeley Nati<strong>on</strong>al Laboratory USA<br />
Chin-Fu TSANG Lawrence Berkeley Nati<strong>on</strong>al Laboratory USA<br />
Frank COCINA Los Alamos Nati<strong>on</strong>al Laboratory USA<br />
Michael Edward COURNOYER Los Alamos Nati<strong>on</strong>al Laboratory USA<br />
121
John ZARLING Los Alamos Nati<strong>on</strong>al Laboratory USA<br />
Yi SU Mississippi State University USA<br />
Geoffrey John PETER Oreg<strong>on</strong> Institute of Technology - Portland Center USA<br />
Chase Collins BOVAIRD Pacific Northwest Nati<strong>on</strong>al Laboratory USA<br />
Danielle JANSIK Pacific Northwest Nati<strong>on</strong>al Laboratory USA<br />
Mark B TRIPLETT Pacific Northwest Nati<strong>on</strong>al Laboratory USA<br />
Dawn M. WELLMAN Pacific Northwest Nati<strong>on</strong>al Laboratory USA<br />
Gary Joseph HANUS Phoenix Soluti<strong>on</strong>s Co USA<br />
Joseph LEGARE S.M. Stoller Corporati<strong>on</strong> USA<br />
Eric OLSON S.M. Stoller Corporati<strong>on</strong> USA<br />
Corey Adam MYERS Studsvik, Inc. USA<br />
Dae Y. CHUNG U.S. Department of Energy USA<br />
Kurt GERDES U.S. Department of Energy USA<br />
Gary L. SMITH U.S. Department of Energy USA<br />
Andrew SZILAGYI U.S. Department of Energy USA<br />
Catherine HANEY U.S. Nuclear Regulatory Commissi<strong>on</strong> USA<br />
Lawrence Edward KOKAJKO U.S. Nuclear Regulatory Commissi<strong>on</strong> USA<br />
Shawn Rochelle SMITH U.S. Nuclear Regulatory Commissi<strong>on</strong> USA<br />
Jo<strong>on</strong>h<strong>on</strong>g AHN University of California, Berkeley USA<br />
John Calvin WALTON University of Texas at El Paso USA<br />
R<strong>on</strong>ald MORRIS Westinghouse Electric Company USA<br />
Wallace M. MAYS WM Mining Company LLC USA<br />
122
ICEM2010 <str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Organizers<br />
<str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> General Chair<br />
Satoru Tanaka, University of Tokyo<br />
Technical Program Chair<br />
Masanori Aritomi, Tokyo Institute of Technology<br />
Technical Program Co-Chair<br />
Anibal L. Taboas, Arg<strong>on</strong>ne Nati<strong>on</strong>al Laboratory<br />
Technical Program Vice-Chair<br />
Kaname Miyahara, Japan Atomic Energy Agency<br />
Administrative Chair<br />
Kazuhiro Takei, Tokyo Electric Power Company<br />
<str<strong>on</strong>g>C<strong>on</strong>ference</str<strong>on</strong>g> Secretary<br />
Hiroyoshi Ueda, Nuclear Waste Management<br />
Organizati<strong>on</strong> of Japan<br />
Exhibiti<strong>on</strong> Secretary<br />
Kiyoshi Fujisaki, Nuclear Waste Management<br />
Organizati<strong>on</strong> of Japan<br />
ASME Project Directors<br />
John Bendo, American Society of Mechanical<br />
Engineers<br />
Vince Dilworth, American Society of Mechanical<br />
Engineers<br />
123<br />
Track Chairs/Co-Chairs<br />
Low/Intermediate-Level Radioactive Waste<br />
Management:<br />
Track Chair<br />
Kunihiro Nakai, JGC Corporati<strong>on</strong><br />
Track Co-Chair<br />
Miklos Garamszeghy, Nuclear Waste Management<br />
Organizati<strong>on</strong><br />
Spent Fuel, Fissile material, Transuranic and<br />
High-Level Radioactive Waste Management:<br />
Track Chair<br />
Kaname Miyahara, Japan Atomic Energy Agency<br />
Track Co-Chair<br />
Stratis Vomvoris, Nagra<br />
Facility Dec<strong>on</strong>taminati<strong>on</strong> and Decommissi<strong>on</strong>ing:<br />
Track Chair<br />
Takeshi Ishikura, Institute of Applied Energy<br />
Track Co-Chair<br />
Toshihiko Higashi, Kansai Electric Power Company<br />
Envir<strong>on</strong>mental Remediati<strong>on</strong>:<br />
Track Chair<br />
Tomohisa Zaitsu, Japan Atomic Energy Agency<br />
Track Co-Chair<br />
Yuu Ishimori, Japan Atomic Energy Agency<br />
Envir<strong>on</strong>mental Management / Public Involvement /<br />
Crosscutting Issues:<br />
Track Chair<br />
Masaki Tsukamoto, Central Research Institute of<br />
Electric Power Industry<br />
Global Partnership and Multi-Nati<strong>on</strong>al Programs:<br />
Track Chair<br />
Hiromi Tanabe, Radioactive Waste Management<br />
Funding and Research Center